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==Subject:==
==Subject:==
Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Pre-op Test Instruction The following approved WBN Unit 2 Pre-op Test Instruction (PTI) is enclosed:
Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Pre-op Test Instruction The following approved WBN Unit 2 Pre-op Test Instruction (PTI) is enclosed:
PTI NUMBER             Rev.                                         TITLE 2-PTI-068-13             0       Shutdown from Outside the Main Control Room If you have any questions, please contact Nick Welch at (423) 365-7820.
PTI NUMBER Rev.
TITLE 2-PTI-068-13 0
Shutdown from Outside the Main Control Room If you have any questions, please contact Nick Welch at (423) 365-7820.
Respectfully, Raymond A. Hruby, Jr.
Respectfully, Raymond A. Hruby, Jr.
General Manager, Technical Services Watts Bar Unit 2 Enclosure
General Manager, Technical Services Watts Bar Unit 2 Enclosure
Line 26: Line 28:
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381
U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381


WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Shutdown from Outside the Main Control Room Instruction No: 2-PTI-068-13 Revision No: 0000 PREPARED BY: R. D. Dobbs                                                     DATE: iJ,32/3/zO-PR INT NAME I SIGNATURE REVIEWED BY: M. David Riden                                                  DATE: i~~ac PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No:               -3     a/0 ?-),
WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Shutdown from Outside the Main Control Room Instruction No: 2-PTI-068-13 Revision No: 0000 PREPARED BY: R. D. Dobbs PR REVIEWED BY: M. David Riden INT NAME I SIGNATURE DATE:
JTG CHAIRMAN:                                                         DATE: Z/2///3 APPROVED BY:                  1F                                        DATE:   /Z'//
iJ,32/3/zO-DATE: i~~ac PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No:
3 a/ 0 ?-),
JTG CHAIRMAN:
APPROVED BY:
1F DATE: Z/2///3 DATE:  
/Z'//
V PFIEOPERAT1ONXL STARTbJP MANAGER TEST RESULTS APPROVAL JTG MEETING No:
V PFIEOPERAT1ONXL STARTbJP MANAGER TEST RESULTS APPROVAL JTG MEETING No:
JTG CHAIRMAN:                                                          DATE:
JTG CHAIRMAN:
APPROVED BY:                                                            DATE:
APPROVED BY:
PREOPERATIONAL STARTUP MANAGER SMP-8.0, Administration of Preoperational Test instructions, Appendix B                   12/07/2010
PREOPERATIONAL STARTUP MANAGER DATE:
DATE:
SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010


WBN         Shutdown from Outside the Main         2-PTI-068-13 Unit 2               Control Room                   Rev. 0000 Page 2 of 36 Revision Log Revision               Affected or Change   Effective     Page Number       Date       Numbers             Description of RevisionlChange 0000                     All     Initial Issue - Unit 2 PTI developed from Unit 1 PTI-068-13, Revision 0.
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 2 of 36 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange 0000 All Initial Issue - Unit 2 PTI developed from Unit 1 PTI-068-13, Revision 0.


WBN                     Shutdown from Outside the Main                                   2-PTI-068-13 Unit 2                                     Control Room                                   Rev. 0000 Page 3 of 36 Table of Contents
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 3 of 36 Table of Contents


==1.0   INTRODUCTION==
==1.0 INTRODUCTION==
.....................................................................................................                      4 1.1   Test Objectives ...............................................                                                                         4 1.2   S co p e ........................................................................     .............................................. . 4
4 1.1 Test Objectives...............................................
4 1.2 S co p e........................................................................  
............................................... 4


==2.0   REFERENCES==
==2.0 REFERENCES==
..........................................................................................................                   5 2.1  Perform ance References.........................................................................................                         5 2.2  Developmental References .......................................                                                                         5 3.0  PRECAUTIONS AND LIMITATIONS ............................................................................                                 8 4.0  PREREQUISITE ACTIONS .........................................................................................                         11 4 .1  P relim inary A ctions ..............................................................................................             . . 11 4.2  Special Tools, Measuring and Test Equipment, Parts, and Supplies ...................... 16 4.3  Field P reparations ................................................................................................               . . 16 4.4  Approvals and Notifications .....................................................................................                       16 5.0  ACCEPTANCE CRITERIA .................................................                         e........................................ 17 6.0  PERFORMANCE ..................................................................................................                         18 7.0  POST PERFORMANCE ACTIVITY ......................................................................                                      .26 8.0  R EC O R DS ..................................................................................................................         26 Appendix A:          Test Procedureslinstructions Reference Review ...............................                                           27 Appendix B:         Temporary Condition Log ...................................................................                             28 Appendix C:          Permanent Plant Instrumentation Log ...............................................                                      29 Figure 1:            RCS Cooldown Rate Graph ................................................................                                33 Figure 2:            Pressurizer Cooldown Rate Graph ....................................................                                    34 Figure 3:           Pressure/Temperature Limit Curves .................................. 35
5 2.1 Perform ance References.........................................................................................
5 2.2 Developmental References.......................................
5 3.0 PRECAUTIONS AND LIMITATIONS............................................................................
8 4.0 PREREQUISITE ACTIONS.........................................................................................
11 4.1 P relim inary A ctions..............................................................................................  
.. 11 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies......................
16 4.3 Field P reparations................................................................................................  
.. 16 4.4 A pprovals and Notifications.....................................................................................
16 5.0 ACCEPTANCE CRITERIA.................................................
e........................................ 17 6.0 PERFORMANCE..................................................................................................
18 7.0 POST PERFORMANCE ACTIVITY......................................................................  
.26 8.0 R EC O R DS..................................................................................................................
26 Appendix A:
Test Procedureslinstructions Reference Review...............................
27 Appendix B:
Temporary Condition Log...................................................................
28 Appendix C:
Permanent Plant Instrumentation Log...............................................
29 Figure 1:
RCS Cooldown Rate Graph................................................................
33 Figure 2:
Pressurizer Cooldown Rate Graph....................................................
34 Figure 3:
Pressure/Temperature Limit Curves.................................. 35


Shutdown from Outside the Main           2-PTI-068-13 Control Room                   Rev. 0000 Page 4 of 36 Date
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 4 of 36 Date


==1.0 INTRODUCTION==
==1.0 INTRODUCTION==
 
1.1 Test Objectives A.
1.1 Test Objectives A. Demonstrate that the Reactor Coolant System (RCS) can be cooled down in a controlled manner from Hot Standby to Hot Shutdown conditions from outside the Main Control Room (MCR), without exceeding Technical Specification cool down limits.
Demonstrate that the Reactor Coolant System (RCS) can be cooled down in a controlled manner from Hot Standby to Hot Shutdown conditions from outside the Main Control Room (MCR), without exceeding Technical Specification cool down limits.
B. Demonstrate the ability to cool down the plant in a controlled manner from the Auxiliary Control Room (ACR) utilizing the Residual Heat Removal (RHR)
B. Demonstrate the ability to cool down the plant in a controlled manner from the Auxiliary Control Room (ACR) utilizing the Residual Heat Removal (RHR)
System.
System.
C. The plant can be maintained in a stable Hot Standby condition from outside the main control room for 30 minutes.
C.
The plant can be maintained in a stable Hot Standby condition from outside the main control room for 30 minutes.
1.2 Scope This Preoperational Test Instruction (PTI) administratively controls performance of 2-TOP-068-01, which incorporates 2-AOI-27, Main Control Room Inaccessibility.
1.2 Scope This Preoperational Test Instruction (PTI) administratively controls performance of 2-TOP-068-01, which incorporates 2-AOI-27, Main Control Room Inaccessibility.


WBN             Shutdown from Outside the Main         2-PTI-068-13 Unit 2                     Control Room                 Rev. 0000 Page 5 of 36 Date
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 5 of 36 Date
 
==2.0  REFERENCES==


2.1   Performance References A. SMP-7.0, Control Of Cleanness, Layup, And Flushing B. SMP-9.0, Conduct of Test C. 2-PTI-068-01, Hot Functional Test D. 2-TOP 068-01, Rev 0, Main Control Room Inaccessibility E. 2-SI-68-44, RCS Temperature/Pressure Limits and Pressurizer Temperature Limits 2.2   Developmental References A. Unit 2 Final Safety Analysis Report (FSAR) - Amendment 109, Table 14.2-1 (Sheets 77, 78 and 79 of 89) Integrated Hot Functional Tests Test Summary B. Drawings
==2.0 REFERENCES==
: 1. Electrical
2.1 Performance References A.
: a. 2-45W751-13, Rev 0, Wiring Diagram 480V Reac Mov Bd 2A1-A Single Line Sh-4
SMP-7.0, Control Of Cleanness, Layup, And Flushing B.
: b. 2-45W751-14, Rev 0, Wiring Diagram 480V Reac Mov Bd 2B1-B Single Line Sh-4
SMP-9.0, Conduct of Test C.
: c. 45B2766-3F, Rev C, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 3F
2-PTI-068-01, Hot Functional Test D.
: d. 45B2766-17F, Rev D, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 17F
2-TOP 068-01, Rev 0, Main Control Room Inaccessibility E.
: e. 45B2768-3F, Rev D, Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 3F
2-SI-68-44, RCS Temperature/Pressure Limits and Pressurizer Temperature Limits 2.2 Developmental References A.
: f. 45B2768-16, Rev 4, F Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 16F
Unit 2 Final Safety Analysis Report (FSAR) - Amendment 109, Table 14.2-1 (Sheets 77, 78 and 79 of 89) Integrated Hot Functional Tests Test Summary B.
Drawings
: 1.
Electrical
: a.
2-45W751-13, Rev 0, Wiring Diagram 480V Reac Mov Bd 2A1-A Single Line Sh-4
: b.
2-45W751-14, Rev 0, Wiring Diagram 480V Reac Mov Bd 2B1-B Single Line Sh-4
: c.
45B2766-3F, Rev C, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 3F
: d.
45B2766-17F, Rev D, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 17F
: e.
45B2768-3F, Rev D, Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 3F
: f.
45B2768-16, Rev 4, F Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 16F


WBN             Shutdown from Outside the Main         2-PTI-068-13 Unit 2                   Control Room                   Rev. 0000 Page 6 of 36 Date 2.2   Developmental References (continued)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 6 of 36 Date 2.2 Developmental References (continued)
: 2. Logic/Control
: 2.
: a. 2-47W610-3-3, Rev 4, Electrical Control Diagram Auxiliary Feedwater System
Logic/Control
: b. 2-47W610-30-2, Rev 2, Electrical Control Diagram Ventilation System
: a.
: c. 2-47W610-47-1, Rev 4, Electrical Control Diagram Turbo Generator Cont Sys
2-47W610-3-3, Rev 4, Electrical Control Diagram Auxiliary Feedwater System
: d. 2-47W610-62-1, Rev 4, Electrical Control Diagram Chemical &
: b.
2-47W610-30-2, Rev 2, Electrical Control Diagram Ventilation System
: c.
2-47W610-47-1, Rev 4, Electrical Control Diagram Turbo Generator Cont Sys
: d.
2-47W610-62-1, Rev 4, Electrical Control Diagram Chemical &
Volume Control Sys
Volume Control Sys
: e. 2-47W610-63-1, Rev 8, Electrical Control Diagram Safety Injection System
: e.
: f. 1-47W610-67-1, Rev 29, Electrical Control Diagram ERCW System
2-47W610-63-1, Rev 8, Electrical Control Diagram Safety Injection System
: g. 2-47W610-68-1, Rev 3, Electrical Control Diagram Reactor Coolant System
: f.
: h. 2-47W610-68-4, Rev 3, Electrical Control Diagram Reactor Coolant System
1-47W610-67-1, Rev 29, Electrical Control Diagram ERCW System
: i. 2-47W610-68-6, Rev 2, Electrical Control Diagram Reactor Coolant System
: g.
: j. 1-47W610-70-1, Rev 28, Electrical Control Diagram Component Cooling Water System
2-47W610-68-1, Rev 3, Electrical Control Diagram Reactor Coolant System
: k. 2-47W610-72-1, Rev 5, Electrical Control Diagram Containment Spray System
: h.
: 1. 2-47W610-74-1, Rev 6, Electrical Control Diagram Residual Heat Removal System
2-47W610-68-4, Rev 3, Electrical Control Diagram Reactor Coolant System
: m. 2-47W610-77-3, Rev 1, Electrical Control Diagram Waste Disposal System
: i.
: 3. Instruments & Controls
2-47W610-68-6, Rev 2, Electrical Control Diagram Reactor Coolant System
: a. 2-47W600-52, Rev 2, Electrical Instruments and Controls
: j.
: b. 2-47W600-55, Rev 0, Electrical Instruments and Controls
1-47W610-70-1, Rev 28, Electrical Control Diagram Component Cooling Water System
: c. 2-47W600-58, Rev 0, Electrical Instruments and Controls
: k.
2-47W610-72-1, Rev 5, Electrical Control Diagram Containment Spray System
: 1.
2-47W610-74-1, Rev 6, Electrical Control Diagram Residual Heat Removal System
: m.
2-47W610-77-3, Rev 1, Electrical Control Diagram Waste Disposal System
: 3.
Instruments & Controls
: a.
2-47W600-52, Rev 2, Electrical Instruments and Controls
: b.
2-47W600-55, Rev 0, Electrical Instruments and Controls
: c.
2-47W600-58, Rev 0, Electrical Instruments and Controls


Shutdown from Outside the Main         2-PTI-068-13 Control Room                 Rev. 0000 Page 7 of 36 Date 2.2 Developmental References (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 7 of 36 Date 2.2 Developmental References (continued)
: d. 47W600-57, Rev 10, Electrical Instruments & Controls
: d.
: e. 47W600-60, Rev 8, Electrical Instruments & Controls C. Documents
47W600-57, Rev 10, Electrical Instruments & Controls
: 1. NRC Regulatory Guide 1.68.2, Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants, Revision 1, July 1978.
: e.
: 2. WBN Unit 2, Technical Specifications, dated 2/28/2012
47W600-60, Rev 8, Electrical Instruments & Controls C.
: a. Section 3.4.3, RCS Pressure and Temperature (P/T) Limits
Documents
: b. Section 5.2.2, Minimum Shift Crew Composition
: 1.
: 3. NPG-SDD-WBN2-68-4001, Rev 2
NRC Regulatory Guide 1.68.2, Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants, Revision 1, July 1978.
: 4. NPG-SDD-WBN2-68-4001, Rev 2, Appendix B, PTLR
: 2.
: 5. WBT-D-2776, Design Specification 67904, Rev 10
WBN Unit 2, Technical Specifications, dated 2/28/2012
: 6. OPDP-1, Rev 23, Conduct of Operations
: a.
: 7. 2-AOI-27, Rev 0, Main Control Room Inaccessibility
Section 3.4.3, RCS Pressure and Temperature (P/T) Limits
: 8. 2-IMI-63.001, Rev 0, Low Steam line Pressure SI Block
: b.
: 9. 2-IMI-63.002, Rev 0, Low Pressurizer Pressure SI Block
Section 5.2.2, Minimum Shift Crew Composition
: 3.
NPG-SDD-WBN2-68-4001, Rev 2
: 4.
NPG-SDD-WBN2-68-4001, Rev 2, Appendix B, PTLR
: 5.
WBT-D-2776, Design Specification 67904, Rev 10
: 6.
OPDP-1, Rev 23, Conduct of Operations
: 7.
2-AOI-27, Rev 0, Main Control Room Inaccessibility
: 8.
2-IMI-63.001, Rev 0, Low Steam line Pressure SI Block
: 9.
2-IMI-63.002, Rev 0, Low Pressurizer Pressure SI Block
: 10. 2-TI-57.002, Rev 0, Verification of Normal Position For Nor-Aux Switches and Various Handswitches
: 10. 2-TI-57.002, Rev 0, Verification of Normal Position For Nor-Aux Switches and Various Handswitches
: 11. 2-TSD-68-6, Rev 0, Test Scoping Document for RCS Cooldown From Hot Functional Testing
: 11.
2-TSD-68-6, Rev 0, Test Scoping Document for RCS Cooldown From Hot Functional Testing


Shutdown from Outside the Main           2-PTI-068-13 Control Room                   Rev. 0000 Page 8 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS A. Standard precautions shall be followed for working around energized electrical equipment in accordance with TVA Safety Manual Procedure 1021.
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 8 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS A.
Standard precautions shall be followed for working around energized electrical equipment in accordance with TVA Safety Manual Procedure 1021.
B. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps are required to be re-verified and a Chronological Test Log (CTL) entry made.
B. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps are required to be re-verified and a Chronological Test Log (CTL) entry made.
C. Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description are sufficient to identify the component. Ifthe component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.
C.
D. All wires removed/lifted from a terminal shall be identified and taped or covered with an insulator to prevent personnel or equipment hazard and possible spurious initiations. The wires should be grouped together and labeled with the work implementing document number that required them to be lifted if left unattended.
Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description are sufficient to identify the component. If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.
E. All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.
D.
F. Problems identified during the test shall be annotated on the Chronological Test Log from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.
All wires removed/lifted from a terminal shall be identified and taped or covered with an insulator to prevent personnel or equipment hazard and possible spurious initiations. The wires should be grouped together and labeled with the work implementing document number that required them to be lifted if left unattended.
G. Observe all Radiation Protection (RP) requirements when working in or near radiological areas.
E.
All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.
F.
Problems identified during the test shall be annotated on the Chronological Test Log from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.
G.
Observe all Radiation Protection (RP) requirements when working in or near radiological areas.
H. Control room observers, who are additional Operations personnel separate from the shutdown crew, shall remain in the Main Control Room. As a minimum, an SRO designated to have the control room command function and and two ROs shall remain in the MCR as control room observers. Additional Operations personnel, who are not confined to the MCR, report to the control room observers and shall NOT assist the shutdown crew nor communicate information to them except in an emergency.
H. Control room observers, who are additional Operations personnel separate from the shutdown crew, shall remain in the Main Control Room. As a minimum, an SRO designated to have the control room command function and and two ROs shall remain in the MCR as control room observers. Additional Operations personnel, who are not confined to the MCR, report to the control room observers and shall NOT assist the shutdown crew nor communicate information to them except in an emergency.


WBN               Shutdown from Outside the Main           2-PTI-068-13 Unit 2                       Control Room                   Rev. 0000 Page 9 of 36 Date 3.0   PRECAUTIONS AND LIMITATIONS (continued)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 9 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)
Control room observers shall assume control of the plant should any emergencies or unsafe conditions arise during this test that are beyond the responsibilities or capabilities of the limited personnel or equipment involved in controlling the plant from the Auxiliary Control Room.
Control room observers shall assume control of the plant should any emergencies or unsafe conditions arise during this test that are beyond the responsibilities or capabilities of the limited personnel or equipment involved in controlling the plant from the Auxiliary Control Room.
J. Termination Criteria: The test shall be terminated and control of the unit returned to the Main Control Room in a safe and orderly manner if any of the following conditions occur:
J.
: 1. SRO in the Main or Auxiliary Control Room or Test Director believes there is a loss of control of any function needed to safely control the unit.
Termination Criteria: The test shall be terminated and control of the unit returned to the Main Control Room in a safe and orderly manner if any of the following conditions occur:
: 2. RCS pressure is less than 1900 psig prior to blocking PZR low pressure Safety Injection.
: 1.
: 3. A condition occurs which has the potential to damage equipment or injure personnel.
SRO in the Main or Auxiliary Control Room or Test Director believes there is a loss of control of any function needed to safely control the unit.
: 4. Safety Injection occurs.
: 2.
: 5. Steam Generator Narrow Range Level less than 0% or greater than 90%.
RCS pressure is less than 1900 psig prior to blocking PZR low pressure Safety Injection.
: 6. Pressurizer Level less than 17% or greater than 92%.
: 3.
: 7. Loss of Offsite Power.
A condition occurs which has the potential to damage equipment or injure personnel.
: 4.
Safety Injection occurs.
: 5.
Steam Generator Narrow Range Level less than 0% or greater than 90%.
: 6.
Pressurizer Level less than 17% or greater than 92%.
: 7.
Loss of Offsite Power.
K. Control room observers shall perform non-safety related activities that would not be required during an actual remote shutdown. These activities provide protection for non-safety related equipment from damage during the transient and include the placement of equipment into standby status when no longer required. These activities shall be recorded in the chronological test log and reviewed at the completion of the test to assess their impact on the validity of the test performance.
K. Control room observers shall perform non-safety related activities that would not be required during an actual remote shutdown. These activities provide protection for non-safety related equipment from damage during the transient and include the placement of equipment into standby status when no longer required. These activities shall be recorded in the chronological test log and reviewed at the completion of the test to assess their impact on the validity of the test performance.
L. The shutdown crew shall not receive communications from the MCR except in an emergency to protect personnel or equipment. Such communications may invalidate the objectives of this test and should be recorded in the chronological test log.
L.
The shutdown crew shall not receive communications from the MCR except in an emergency to protect personnel or equipment. Such communications may invalidate the objectives of this test and should be recorded in the chronological test log.
M. Only that equipment for which credit would be taken in performing an actual remote plant shutdown shall be used for this test in order to satisfy the Acceptance Criteria.
M. Only that equipment for which credit would be taken in performing an actual remote plant shutdown shall be used for this test in order to satisfy the Acceptance Criteria.


Shutdown from Outside the Main         2-PTI-068-13 Control Room                 Rev. 0000 Page 10 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 10 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)
N. Reactor Coolant temperature shall not be reduced at a rate that exceeds Technical Specification cooldown limits of 100°F in any one hour period.
N. Reactor Coolant temperature shall not be reduced at a rate that exceeds Technical Specification cooldown limits of 100°F in any one hour period.
Cooldown should be performed at a rate of no more than 50 °F/hour.
Cooldown should be performed at a rate of no more than 50°F/hour.
: 0. Pressurizer temperature shall not be reduced at a rate that exceeds 200OF in any one hour period. Pressurizer cooldown rate should not exceed 100IF in any one hour.
: 0.
P. Reactor Coolant System temperature and pressure shall be determined at least once each 30 minutes to be within the Pressure/Temperature Curve for plant cooldown.
Pressurizer temperature shall not be reduced at a rate that exceeds 200OF in any one hour period. Pressurizer cooldown rate should not exceed 100IF in any one hour.
Q. Pressurizer Spray should NOT normally be initiated if the temperature difference between the Pressurizer and spray fluid is greater than 100 0F, although higher differential temperatures are acceptable for a few cycles in the life of the plant. Under no circumstances shall Pressurizer Spray be intiated if the temperature difference between the Pressurizer and the spray fluid is equal to or greater than 2600 F. Any initations where the temperature difference is greater than 260OF shall be reported to Engineering for evaluation and accounted for in thermal cycle monitoring in the licensing basis. Auxiliary spray flow from charging pump should be intiated slowly.
P.
R. 2-PTI-068-01, Hot Functional Test (HFT), contains prerequisites, the lineups for plant support systems, instrumentation, and controls associated with HFT, which includes this PTI.
Reactor Coolant System temperature and pressure shall be determined at least once each 30 minutes to be within the Pressure/Temperature Curve for plant cooldown.
S. During the performance of 2-TOP-68-01, Operations personnel are required to initial and date the steps as they are performed. In addition, the Test Engineer (TE) shall record in the Chronological Test Log the actual equipment or equipment loop which was used to perform this test.
Q.
Pressurizer Spray should NOT normally be initiated if the temperature difference between the Pressurizer and spray fluid is greater than 100 0F, although higher differential temperatures are acceptable for a few cycles in the life of the plant. Under no circumstances shall Pressurizer Spray be intiated if the temperature difference between the Pressurizer and the spray fluid is equal to or greater than 2600F. Any initations where the temperature difference is greater than 260OF shall be reported to Engineering for evaluation and accounted for in thermal cycle monitoring in the licensing basis. Auxiliary spray flow from charging pump should be intiated slowly.
R.
2-PTI-068-01, Hot Functional Test (HFT), contains prerequisites, the lineups for plant support systems, instrumentation, and controls associated with HFT, which includes this PTI.
S.
During the performance of 2-TOP-68-01, Operations personnel are required to initial and date the steps as they are performed. In addition, the Test Engineer (TE) shall record in the Chronological Test Log the actual equipment or equipment loop which was used to perform this test.


WBN             Shutdown from Outside the Main             2-PTI-068-13 Unit 2                     Control Room                     Rev. 0000 Page 11 of 36 Date 4.0     PREREQUISITE ACTIONS NOTE Preliminary action steps may be performed in any order with Test Directors approval.
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 11 of 36 Date 4.0 PREREQUISITE ACTIONS NOTE Preliminary action steps may be performed in any order with Test Directors approval.
4.1     Preliminary Actions
4.1 Preliminary Actions
[1]   VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.
[1]
[2]   OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the PTI performance.
VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.
[3]   ENSURE changes to the references listed on Appendix A, Test Procedure/Instruction Reference Review, have been reviewed, and determined not to adversely affect the test performance.
[2]
[4]   VERIFY current revisions and change paper for referenced drawings has been reviewed and determined NOT to adversely affect the test performance, and ATTACH documentation of current drawing revision numbers and change paper that were reviewed to the data package.
OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the PTI performance.
[5]   EVALUATE punchlist items on Open Watts Bar Integrated Task Equipment List (WITEL) and ENSURE they will NOT adversely affect the test performance.
[3]
[6]   ENSURE the minimum shutdown crew composition, as defined by OPDP-1, Conduct of Operations, is available for the performance of this test: Shift Manager (SRO) = 1, Unit Supervisor (SRO) = 1, Shift Technical Advisor (STA) =1, Reactor Operator (RO) = 2, and Assistant Unit Operator (AUO) = 5].
ENSURE changes to the references listed on Appendix A, Test Procedure/Instruction Reference Review, have been reviewed, and determined not to adversely affect the test performance.
[4]
VERIFY current revisions and change paper for referenced drawings has been reviewed and determined NOT to adversely affect the test performance, and ATTACH documentation of current drawing revision numbers and change paper that were reviewed to the data package.
[5]
EVALUATE punchlist items on Open Watts Bar Integrated Task Equipment List (WITEL) and ENSURE they will NOT adversely affect the test performance.
[6]
ENSURE the minimum shutdown crew composition, as defined by OPDP-1, Conduct of Operations, is available for the performance of this test: Shift Manager (SRO) = 1, Unit Supervisor (SRO) = 1, Shift Technical Advisor (STA) =1, Reactor Operator (RO) = 2, and Assistant Unit Operator (AUO) = 5].


WBN               Shutdown from Outside the Main         2-PTI-068-13 Unit 2                       Control Room               Rev. 0000 Page 12 of 36 Date 4.1   Preliminary Actions (continued).
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 12 of 36 Date 4.1 Preliminary Actions (continued).
    *[7]   ENSURE the minimum observation crew is available for performance of this test: SRO designated to have the control room command function = 1, UOs for control board oversight and 2-SI-68-44 performance = 2.
*[7]
[8]   ENSURE required Component Testing has been completed prior to start of test.
ENSURE the minimum observation crew is available for performance of this test: SRO designated to have the control room command function = 1, UOs for control board oversight and 2-SI-68-44 performance = 2.
[9]   ENSURE outstanding Design Change Notices (DCN's),
[8]
ENSURE required Component Testing has been completed prior to start of test.
[9]
ENSURE outstanding Design Change Notices (DCN's),
Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.
Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.
[10] ENSURE a review of outstanding Clearances has been coordinated with Operations for impact to the test performance, and RECORD in Appendix B, Temporary Condition Log.
[10]
[11] VERIFY System cleanness as required for the performance of this test has been completed in accordance with SMP-7.0.
ENSURE a review of outstanding Clearances has been coordinated with Operations for impact to the test performance, and RECORD in Appendix B, Temporary Condition Log.
[12] VERIFY plant instruments, listed on Appendix C, Permanent Plant Instrumentation Log, are placed in service and are within their calibration interval.
[11]
[13] VERIFY Measuring and Test Equipment (M&TE) required for test performance has been (as required) filled, vented, place in service and recorded on Measuring and Test Equipment Log in SMP-9.0.
VERIFY System cleanness as required for the performance of this test has been completed in accordance with SMP-7.0.
[14] VERIFY M&TE calibration due dates will support the completion of this test performance.
[12]
[15] VERIFY the Unit 2 Plant Computer System 261 is in service.
VERIFY plant instruments, listed on Appendix C, Permanent Plant Instrumentation Log, are placed in service and are within their calibration interval.
[16] VERIFY the Unit 2 Annunciator System 55 is in service.
[13]
VERIFY Measuring and Test Equipment (M&TE) required for test performance has been (as required) filled, vented, place in service and recorded on Measuring and Test Equipment Log in SMP-9.0.
[14]
VERIFY M&TE calibration due dates will support the completion of this test performance.
[15]
VERIFY the Unit 2 Plant Computer System 261 is in service.
[16]
VERIFY the Unit 2 Annunciator System 55 is in service.


Shutdown from Outside the Main           2-PTI-068-13 Control Room                   Rev. 0000 Page 13 of 36 Date 4.1 Preliminary Actions (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 13 of 36 Date 4.1 Preliminary Actions (continued)
[17] ENSURE System 55, Annunciator and Sequential Events Recording System applicable Terminal Block (TBK) switches [in Panel 2-M-21] are ON, the applicable Master Switches are ON, and window software input(s) are ENABLED for the following Annunciator windows:
[17]
A. 2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-D, M-1 THRU M-6 MOTOR OVERLOAD B. 2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-E, M-1 THRU M-6 MOTOR TRIPOUT C. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 95-E, RCP BD 2A UV/CNTL PWR FAILURE/TRANSFER D. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 96-E, RCP BD 2B UV/CNTL PWR FAILURE/TRANSFER E. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 97-E, RCP BD 2C UV/CNTL PWR FAILURE/TRANSFER F. 2-XA-55-5B Annunciator Panel in 2-M-5, Window 98-E, RCP BD 2D UV/CNTL PWR FAILURE/TRANSFER G. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-A, RCP BD 2AI2BI2CI2D H. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-B, ACR PNL 2-L-1 1A
ENSURE System 55, Annunciator and Sequential Events Recording System applicable Terminal Block (TBK) switches [in Panel 2-M-21] are ON, the applicable Master Switches are ON, and window software input(s) are ENABLED for the following Annunciator windows:
: 1. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-C, ACR PNL 2-L-1 1B
A.
[18] VERIFY the following annunciator windows on 2-M-6 are clear:
2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-D, M-1 THRU M-6 MOTOR OVERLOAD B.
A. Window 148-B, ACR PNL 2-L-1 1A B. Window 148-C, ACR PNL 2-L-11B
2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-E, M-1 THRU M-6 MOTOR TRIPOUT C.
[19] ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.
2-XA-55-5B Annunciator Panel in 2-M-5, Window 95-E, RCP BD 2A UV/CNTL PWR FAILURE/TRANSFER D.
[20] ENSURE the test performance personnel have been notified and are available to support the test.
2-XA-55-5B Annunciator Panel in 2-M-5, Window 96-E, RCP BD 2B UV/CNTL PWR FAILURE/TRANSFER E.
2-XA-55-5B Annunciator Panel in 2-M-5, Window 97-E, RCP BD 2C UV/CNTL PWR FAILURE/TRANSFER F.
2-XA-55-5B Annunciator Panel in 2-M-5, Window 98-E, RCP BD 2D UV/CNTL PWR FAILURE/TRANSFER G.
2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-A, RCP BD 2AI2BI2CI2D H. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-B, ACR PNL 2-L-1 1A
: 1.
2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-C, ACR PNL 2-L-1 1 B
[18]
VERIFY the following annunciator windows on 2-M-6 are clear:
A.
Window 148-B, ACR PNL 2-L-1 1A B.
Window 148-C, ACR PNL 2-L-11B
[19]
ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.
[20]
ENSURE the test performance personnel have been notified and are available to support the test.


WBN             Shutdown from Outside the Main           2-PTI-068-13 Unit 2                     Control Room                   Rev. 0000 Page 14 of 36 Date 4.1   Preliminary Actions (continued)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 14 of 36 Date 4.1 Preliminary Actions (continued)
[211 PERFORM a pretest walk down on equipment to be tested to ensure no conditions exist that will impact test performance.
[211 PERFORM a pretest walk down on equipment to be tested to ensure no conditions exist that will impact test performance.
[22] CONDUCT a pretest briefing with Test and Operations personnel in accordance with SMP-9.0.
[22]
[231 ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the Backup Control Center sound powered phone system:
CONDUCT a pretest briefing with Test and Operations personnel in accordance with SMP-9.0.
A. 6.9 KV Shutdown Board Room (Train A)
[231 ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the Backup Control Center sound powered phone system:
B. 6.9 KV Shutdown Board Room (Train B)
A.
C. 480V Shutdown Board Room (Unit 2)
6.9 KV Shutdown Board Room (Train A)
D. Reactor MOV Board Room (Unit 2)
B.
[24] ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the plant telephone system:
6.9 KV Shutdown Board Room (Train B)
A. 6.9 KV Shutdown Board Room (Train A)
C.
B. 6.9 KV Shutdown Board Room (Train B)
480V Shutdown Board Room (Unit 2)
C. 480V Shutdown Board Room (Unit 2)
D.
D. Reactor MOV Board Room (Unit 2)
Reactor MOV Board Room (Unit 2)
E. 6.9 KV Reactor Coolant Pump (RCP) Boards F. Main Control Room G. Auxiliary Building, EL 692', East side, near Turbine Driven (TD) Auxiliary Feedwater (AFW) pump area.
[24]
ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the plant telephone system:
A.
6.9 KV Shutdown Board Room (Train A)
B.
6.9 KV Shutdown Board Room (Train B)
C.
480V Shutdown Board Room (Unit 2)
D.
Reactor MOV Board Room (Unit 2)
E.
6.9 KV Reactor Coolant Pump (RCP) Boards F.
Main Control Room G.
Auxiliary Building, EL 692', East side, near Turbine Driven (TD) Auxiliary Feedwater (AFW) pump area.


Shutdown from Outside the Main           2-PTI-068-13 Control Room                 Rev. 0000 Page 15 of 36 Date 4.1 Preliminary Actions (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 15 of 36 Date 4.1 Preliminary Actions (continued)
[25] VERIFY HFT is being performed with the RCS at Hot Standby Conditions, and.'
[25]
VERIFY HFT is being performed with the RCS at Hot Standby Conditions, and.'
RECORD RCS Temperature from 2-TI-68-1, LOOP 1 HL TEMP, on 2-M-5.
RECORD RCS Temperature from 2-TI-68-1, LOOP 1 HL TEMP, on 2-M-5.
OF   (greater than or equal to 350°F)
OF (greater than or equal to 350°F)
[26] ESTABLISH additional qualified Operations crew as directed by the Shift Manager (SM) in the MCR who can take control of the plant should any emergencies or unsafe conditions arise during the performance of this test. (See Precautions And Limitations 3.0H)
[26]
[27] VERIFY/CLOSE the following breakers at 480V Reactor MOV Board 2A1-A (2-MCC-213-A1):
ESTABLISH additional qualified Operations crew as directed by the Shift Manager (SM) in the MCR who can take control of the plant should any emergencies or unsafe conditions arise during the performance of this test. (See Precautions And Limitations 3.0H)
A. SIS CL ACCUM 3 OUT ISOL, (2-FCV-63-80), Shunt Trip Breaker, 2-BKR-63-80A, at Cubicle 17F2.
[27]
B. SIS CL ACCUM 1 OUT ISOL, (2-FCV-63-1 18), Shunt Trip Breaker, 2-BKR-63-118A, at Cubicle 3F2.
VERIFY/CLOSE the following breakers at 480V Reactor MOV Board 2A1-A (2-MCC-213-A1):
[28] VERIFYICLOSE the following breakers at 480V Reactor MOV Board 2B1-B (2-MCC-213-B1):
A.
A. SIS CL ACCUM 2 OUT ISOL, (2-FCV-63-98), Shunt Trip Breaker, 2-BKR-63-98A, at Cubicle 3F2.
SIS CL ACCUM 3 OUT ISOL, (2-FCV-63-80), Shunt Trip Breaker, 2-BKR-63-80A, at Cubicle 17F2.
B. SIS CL ACCUM 4 OUT ISOL, (2-FCV-63-67), Shunt Trip Breaker, 2-BKR-63-67A, at Cubicle 16F2.
B.
[29] VERIFY 2-PTI-068-01 prerequisites are complete for the 557°F plateau.
SIS CL ACCUM 1 OUT ISOL, (2-FCV-63-1 18), Shunt Trip Breaker, 2-BKR-63-118A, at Cubicle 3F2.
[30] VERIFY the Condensate Storage Tank B is at normal operating level. (Greater than 200,000 gallons). .
[28]
[31] ENSURE the System and Equipment Status Control, NGDC-PI-8, Preoperational Configuration Log has been evaluated.
VERIFYICLOSE the following breakers at 480V Reactor MOV Board 2B1-B (2-MCC-213-B1):
A.
SIS CL ACCUM 2 OUT ISOL, (2-FCV-63-98), Shunt Trip Breaker, 2-BKR-63-98A, at Cubicle 3F2.
B.
SIS CL ACCUM 4 OUT ISOL, (2-FCV-63-67), Shunt Trip Breaker, 2-BKR-63-67A, at Cubicle 16F2.
[29]
VERIFY 2-PTI-068-01 prerequisites are complete for the 557°F plateau.
[30]
VERIFY the Condensate Storage Tank B is at normal operating level. (Greater than 200,000 gallons)..
[31]
ENSURE the System and Equipment Status Control, NGDC-PI-8, Preoperational Configuration Log has been evaluated.


WBN             Shutdown from Outside the Main       2-PTI-068-13 Unit 2                   Control Room               Rev. 0000 Page 16 of 36 Date 4.2   Special Tools, Measuring and Test Equipment, Parts, and Supplies
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 16 of 36 Date 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies
[1]   VERIFY a M&TE Qualified Stopwatch, 0-60 minutes,
[1]
            +/-0.1 second accuracy is available.
VERIFY a M&TE Qualified Stopwatch, 0-60 minutes,
[2]   VERIFY four sets of Backup (Shutdown) Control Center sound powered telephones are available.
+/-0.1 second accuracy is available.
[3]   ESTABLISH a means of identifying the Main Control Room observation crew and Aux Control Room shutdown crew for this test performance.
[2]
4.3   Field Preparations None 4.4 Approvals and Notifications
VERIFY four sets of Backup (Shutdown) Control Center sound powered telephones are available.
[1]   OBTAIN permission of the Preoperational Startup Manager to start the test.
[3]
Preoperational Startup Manager           Date Signature
ESTABLISH a means of identifying the Main Control Room observation crew and Aux Control Room shutdown crew for this test performance.
[2]   OBTAIN the Unit 2 (U2) Supervisors (US/SRO) or Shift Managers (SM) authorization.
4.3 Field Preparations None 4.4 Approvals and Notifications
U2 US/SRO/SM Signature                 Date
[1]
OBTAIN permission of the Preoperational Startup Manager to start the test.
Preoperational Startup Manager Signature Date
[2]
OBTAIN the Unit 2 (U2) Supervisors (US/SRO) or Shift Managers (SM) authorization.
U2 US/SRO/SM Signature Date


WBN               Shutdown from Outside the Main       2-PTI-068-13 Unit 2                       Control Room               Rev. 0000 Page 17 of 36 Date 5.0   ACCEPTANCE CRITERIA A. Plant cooldown is performed from outside the MCR from Hot Standby [TAVG of 450°F (425°F - 4750 F)] to Hot Shutdown (TAVG between 200°F and 350'F) conditions, without exceeding the Technical Specification cooldown rate limit of 100°F/Hr as plotted on Figure 1. (Steps 6.0[8]F and 6.0[13])
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 17 of 36 5.0 Date ACCEPTANCE CRITERIA A.
B. The RHR System is used to cool down the Reactor Coolant System at least 50 0 F, from outside the MCR, without exceeding the Technical Specification cooldown rate limit of 100°FIHr as plotted on Figure 1. (Steps 6.0[12]D and 6.0[13])
Plant cooldown is performed from outside the MCR from Hot Standby [TAVG of 450°F (425°F - 4750F)] to Hot Shutdown (TAVG between 200°F and 350'F) conditions, without exceeding the Technical Specification cooldown rate limit of 1 00°F/Hr as plotted on Figure 1. (Steps 6.0[8]F and 6.0[13])
B.
The RHR System is used to cool down the Reactor Coolant System at least 50 0F, from outside the MCR, without exceeding the Technical Specification cooldown rate limit of 100°FIHr as plotted on Figure 1. (Steps 6.0[12]D and 6.0[13])


WBN               Shutdown from Outside the Main         2-PTI-068-13 Unit 2                     Control Room                   Rev. 0000 Page 18 of 36 Date 6.0   PERFORMANCE NOTES
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 18 of 36 Date 6.0 PERFORMANCE NOTES
: 1) Any activities performed that are outside the scope of this test will be recorded in the Chronological Test Log by the TE and evaluated for their impact on the validity of total test performance after this PTI is completed.
: 1) Any activities performed that are outside the scope of this test will be recorded in the Chronological Test Log by the TE and evaluated for their impact on the validity of total test performance after this PTI is completed.
: 2) Step 6.0[1] ensures Tech Spec compliance and must not be communicated with shutdown crew unless limit is about to be exceeded.
: 2)
[1]     INITIATE applicable sections of 2-SI-68-44, RCS Temperature/Pressure Limits And Pressurizer Temperature Limits, and ACCESS ICS screens HC and HCRGRPH to monitor RCS and Pzr Temperature/Pressure Limits from ICS to ensure Tech Spec criteria NOT violated.
Step 6.0[1] ensures Tech Spec compliance and must not be communicated with shutdown crew unless limit is about to be exceeded.
MCR Observer                           Date
[1]
[2]   ANNOUNCE over the public address system to notify plant personnel of the control transfer from the U-2 Main Control Room to the U-2 Auxiliary Control Room.
INITIATE applicable sections of 2-SI-68-44, RCS Temperature/Pressure Limits And Pressurizer Temperature Limits, and ACCESS ICS screens HC and HCRGRPH to monitor RCS and Pzr Temperature/Pressure Limits from ICS to ensure Tech Spec criteria NOT violated.
[3]   ELECTRONICALLY MARK the following MCR chart recorders by depressing the keyboard button and entering 2-PTI-068-13 denoting the start of process control from outside the Main Control Room:
MCR Observer Date
A. Pressurizer (PZR) Pressure (2-PR-68-340) [2-M-5]
[2]
B. PZR Level (2-LR-68-339) [2-M-5]
ANNOUNCE over the public address system to notify plant personnel of the control transfer from the U-2 Main Control Room to the U-2 Auxiliary Control Room.
C. HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
[3]
D. HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
ELECTRONICALLY MARK the following MCR chart recorders by depressing the keyboard button and entering 2-PTI-068-13 denoting the start of process control from outside the Main Control Room:
E. HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
A.
F. HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]
Pressurizer (PZR) Pressure (2-PR-68-340) [2-M-5]
B.
PZR Level (2-LR-68-339) [2-M-5]
C.
HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
D.
HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
E.
HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
F.
HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]


WBN           Shutdown from Outside the Main           2-PTI-068-13 Unit 2                   Control Room                 Rev. 0000 Page 19 of 36 Date 6.0   PERFORMANCE (continued)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 19 of 36 Date 6.0 PERFORMANCE (continued)
G. HL Pressure (2-PR-68-63) [2-M-5]
G.
HL Pressure (2-PR-68-63) [2-M-5]
H. Steam Generator (SG) Level % (2-LR-3-43) [2-M-4]
H. Steam Generator (SG) Level % (2-LR-3-43) [2-M-4]
I. SG Level % (2-LR-3-98) [2-M-4]
I.
J. SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]
SG Level % (2-LR-3-98) [2-M-4]
J.
SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]
[4] TRANSFER process control from the MCR to ACR in accordance with 2-TOP-068-01, Section 2.1.
[4]
A. RECORD time at which all Aux Control Room shutdown personnel are assembled in the Aux Control Room.
TRANSFER process control from the MCR to ACR in accordance with 2-TOP-068-01, Section 2.1.
Time B. RECORD time at which each 2-TOP-068-01 checklist (ACR, #1, #2, and #3) is complete below:
A.
Checklist             Time             Initial ACR
RECORD time at which all Aux Control Room shutdown personnel are assembled in the Aux Control Room.
                          #1
Time B.
                          #2
RECORD time at which each 2-TOP-068-01 checklist (ACR, #1, #2, and #3) is complete below:
                          #3 C. RECORD time process control transfer from the MCR to ACR is complete, the time the last checklist (ACR, #1, #2, and #3) is complete from step above.
Checklist Time Initial ACR
Process Control in ACR                     Time
#1
#2
#3 C.
RECORD time process control transfer from the MCR to ACR is complete, the time the last checklist (ACR, #1, #2, and #3) is complete from step above.
Process Control in ACR Time


WBN           Shutdown from Outside the Main         2-PTI-068-13 Unit 2                   Control Room                 Rev. 0000 Page 20 of 36 Date 6.0     PERFORMANCE (continued)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 20 of 36 Date 6.0 PERFORMANCE (continued)
[5] ESTABLISH Hot Standby conditions in accordance with 2-TOP-068-01, and START stopwatch when stable Hot Standby conditions are attained.
[5]
ESTABLISH Hot Standby conditions in accordance with 2-TOP-068-01, and START stopwatch when stable Hot Standby conditions are attained.
M&TE
M&TE
[6] MAINTAIN stable Hot Standby conditions from the ACR for a minimum of 30 minutes to ensure control of the unit in accordance with 2-TOP-068-01 and, RECORD total time Hot Standby maintained before commencing plant cooldown.
[6]
Elapsed Time                   minutes S CCAUTION RCS Cooldown rate should not exceed 50°F/hour.
MAINTAIN stable Hot Standby conditions from the ACR for a minimum of 30 minutes to ensure control of the unit in accordance with 2-TOP-068-01 and, RECORD total time Hot Standby maintained before commencing plant cooldown.
[7] MONITOR appropriate Cooldown Pressure-Temperature Curves of the appropriate Figure 3 Curves, and PLOT every 30 minutes during all cooldown operations to ensure acceptable region maintained.
Elapsed Time minutes S CCAUTION RCS Cooldown rate should not exceed 50°F/hour.
[8] INITIATE plant cooldown from Hot Standby to Hot Shutdown conditions in accordance with 2-TOP-068-01, Section 2.2, and PERFORM the following:
[7]
A. RECORD RCS Loop temperatures (Hot Standby
MONITOR appropriate Cooldown Pressure-Temperature Curves of the appropriate Figure 3 Curves, and PLOT every 30 minutes during all cooldown operations to ensure acceptable region maintained.
                  -greater than or equal to 350 0F)
[8]
UNID         Temperature       Panel       Initial CV 2-T1-68-1C                 OF     2-L-10 2-TI-68-24C                 oF     2-L-1 0 2-TI-68-43C                 OF     2-L-10 2-TI-68-65C                 OF     2-L-10
INITIATE plant cooldown from Hot Standby to Hot Shutdown conditions in accordance with 2-TOP-068-01, Section 2.2, and PERFORM the following:
A.
RECORD RCS Loop temperatures (Hot Standby
-greater than or equal to 3500F)
UNID Temperature Panel Initial CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C oF 2-L-1 0 2-TI-68-43C OF 2-L-10 2-TI-68-65C OF 2-L-10


Shutdown from Outside the Main             2-PTI-068-13 Control Room                  Rev. 0000 Page 21 of 36 Date 6.0 PERFORMANCE (continued)
Shutdown from Outside the Main Control Room 2-PTI-068-13 Rev. 0000 Page 21 of 36 Date 6.0 PERFORMANCE (continued)
B. RECORD RCS average temperature from Step 6.0[8]A by adding all four temperatures and dividing by four.
B.
Average Temp.               OF Initials         Date Verified          Date C. START stopwatch, and PLOT the following temperatures at time zero and at 15 minute intervals:
RECORD RCS average temperature from Step 6.0[8]A by adding all four temperatures and dividing by four.
            "    RCS temperature using 2-TI-68-1 C on Figure 1.
Average Temp.
            "    PZR temperature as determined by Pressurizer Pressure indication for T-sat on Figure 2 using steam tables located in storage locker.
OF Initials Verified Date Date C.
D. RECORD RCS loop temperatures when Hot Shutdown condition is established. (less than 3500 F)
START stopwatch, and PLOT the following temperatures at time zero and at 15 minute intervals:
UNID           Temperature       Panel         Initial,   CV 2-T1-68-1C                   OF     2-L-10 2-TI-68-24C                 -F     2-L-1 0 2-TI-68-43C                 OF     2-L-1 0 2-TI-68-65C                 OF     2-L-1 0
RCS temperature using 2-TI-68-1 C on Figure 1.
PZR temperature as determined by Pressurizer Pressure indication for T-sat on Figure 2 using steam tables located in storage locker.
D. RECORD RCS loop temperatures when Hot Shutdown condition is established. (less than 3500F)
UNID Temperature Panel
: Initial, CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C  
-F 2-L-1 0 2-TI-68-43C OF 2-L-1 0 2-TI-68-65C OF 2-L-1 0


Shutdown from Outside the Main           2-PTI-068-13 Control Room                 Rev. 0000 Page 22 of 36 Date 6.0     PERFORMANCE (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 22 of 36 Date 6.0 PERFORMANCE (continued)
E. RECORD RCS average temperature from Step 6.0[8]D by adding all four temperatures and dividing by four.
E.
Average Temp.               OF Initials             Date Verified              Date F. VERIFY all recorded temperatures in Step 6.0[8]D are less than 350 0 F. (Acc Crit 5.OA)
RECORD RCS average temperature from Step 6.0[8]D by adding all four temperatures and dividing by four.
Average Temp.
OF Initials Verified Date Date F.
VERIFY all recorded temperatures in Step 6.0[8]D are less than 3500F. (Acc Crit 5.OA)
CAUTION RCS Cooldown rate should not exceed 50°F/hour.
CAUTION RCS Cooldown rate should not exceed 50°F/hour.
NOTE Plant conditions warrant that only one train of RHR is needed to perform cooldown during HFT, and should be identified in the Chronological Test Log by the TE.
NOTE Plant conditions warrant that only one train of RHR is needed to perform cooldown during HFT, and should be identified in the Chronological Test Log by the TE.
[9]   ESTABLISH RCS cooldown utilizing RHR in accordance with 2-TOP-068-01.
[9]
[10]   WHEN RHR System is placed in service, THEN
ESTABLISH RCS cooldown utilizing RHR in accordance with 2-TOP-068-01.
                .RECORD RCS loop temperatures UNID           Temperature     Panel         " Initial :7..!:'CV 2-T1-68-1C             OF         2-L-10 2-TI-68-24C           TF         2-L-10 2-TI-68-43C           TF         2-L-10 2-TI-68-65C           TF         2-L-10
[10]
WHEN RHR System is placed in service, THEN
.RECORD RCS loop temperatures UNID Temperature Panel Initial :7..!:'CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C TF 2-L-10 2-TI-68-43C TF 2-L-10 2-TI-68-65C TF 2-L-10


Shutdown from Outside the Main           2-PTI-068-13 Control Room                 Rev. 0000 Page 23 of 36 Date 6.0 PERFORMANCE (continued)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 23 of 36 Date 6.0 PERFORMANCE (continued)
[11] RECORD RCS average temperature from Step 6.0[10] by adding all four temperatures and dividing by four.
[11]
Average Temp.               OF Initials         Date Verified          Date
RECORD RCS average temperature from Step 6.0[10] by adding all four temperatures and dividing by four.
[12] LOWER RCS average temperature to 2750 F (270°F - 280°F) using RHR System from outside the MCR in accordance with 2-TOP-068-01, Section 2.2.
Average Temp.
A. RECORD RCS loop temperatures:
OF Initials Verified Date Date
                        .UNID         Temperature.:     Panel.         Initial   CV 2-T1-68-1C                 OF     2-L-10 2-TI-68-24C                 OF     2-L-1 0 2-TI-68-43C                 OF     2-L-10 2-TI-68-65C                 OF     2-L-10 B. RECORD RCS average temperature from Step 6.0[12]A by adding all four temperatures and dividing by four.
[12]
Average Temp.               OF Initials         Date Verified         Date
LOWER RCS average temperature to 2750F (270°F - 280°F) using RHR System from outside the MCR in accordance with 2-TOP-068-01, Section 2.2.
A.
RECORD RCS loop temperatures:
.UNID Temperature.:
Panel.
Initial CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C OF 2-L-1 0 2-TI-68-43C OF 2-L-10 2-TI-68-65C OF 2-L-10 B.
RECORD RCS average temperature from Step 6.0[12]A by adding all four temperatures and dividing by four.
Average Temp.
OF Initials Date Verified Date


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WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 24 of 36 Date 6.0 PERFORMANCE (continued)
C. DETERMINE temperature in Step 6.0[10] minus temperature in Step 6.0[12]A:
C.
Temperatures UNID           (Step 6.0[10] -Step 6.0[12])     INITIAL   CV 2-T1-68-1C                                     OF 2-TI-68-24C                                   OF 2-TI-68-43C                                   OF 2-TI-68-65C                                   OF D. VERIFY all calculated temperatures recorded in Step 6.0[12]C are greater than or equal to 50 0 F.
DETERMINE temperature in Step 6.0[10] minus temperature in Step 6.0[12]A:
Temperatures UNID (Step 6.0[10] -Step 6.0[12])
INITIAL CV 2-T1-68-1C OF 2-TI-68-24C OF 2-TI-68-43C OF 2-TI-68-65C OF D. VERIFY all calculated temperatures recorded in Step 6.0[12]C are greater than or equal to 500F.
(Acc Crit 5.0B)
(Acc Crit 5.0B)
[13] VERIFY cooldown rate plotted on Figure 1 does not exceed the Technical Specification limit of 1OO0 F/hour.
[13]
VERIFY cooldown rate plotted on Figure 1 does not exceed the Technical Specification limit of 1OO0 F/hour.
(Acc Crit 5.0B)
(Acc Crit 5.0B)
[14] STOP the stopwatch, and DISCONTINUE plotting RCS temperature.
[14]
[15] TRANSFER process control from the ACR to MCR in accordance with 2-TOP-068-01, Section 2.3.
STOP the stopwatch, and DISCONTINUE plotting RCS temperature.
[15]
TRANSFER process control from the ACR to MCR in accordance with 2-TOP-068-01, Section 2.3.


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WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 25 of 36 Date 6.0 PERFORMANCE (continued)
[16] ELECTRONICALLY MARK the following MCR recorders denoting the end of process control from the Auxiliary Control Room:
[16]
A. PZR Pressure (2-PR-68-340).[2-M-5]
ELECTRONICALLY MARK the following MCR recorders denoting the end of process control from the Auxiliary Control Room:
B. PZR Level (2-LR-68-339) [2-M-5]
A.
C. HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
PZR Pressure (2-PR-68-340).[2-M-5]
D. HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
B.
E. HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
PZR Level (2-LR-68-339) [2-M-5]
F. HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]
C.
G. HL Pressure (2-PR-68-63) [2-M-5]
HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]
H. SG Level % (2-LR-3-43) [2-M-41 I. SG Level % (2-LR-3-98) [2-M-41 J. SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]
D.
HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]
E.
HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]
F.
HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]
G.
HL Pressure (2-PR-68-63) [2-M-5]
H. SG Level % (2-LR-3-43) [2-M-41 I.
SG Level % (2-LR-3-98) [2-M-41 J.
SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]
K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]


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WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 26 of 36 Date 7.0 POST PERFORMANCE ACTIVITY
[1]   VERIFY the following:
[1]
A. Post-test calibration of the M&TE used to record quantitative acceptance criteria has been satisfactorily performed.
VERIFY the following:
B. The results recorded on Measuring and Test Equipment (M&TE) Log in SMP-9.0.
A.
[2]   VERIFY Post-test calibration of permanent plant instruments used to record quantitative acceptance criteria has been satisfactorily performed and RECORD the results on Appendix C, Permanent Plant Instrumentation Log.
Post-test calibration of the M&TE used to record quantitative acceptance criteria has been satisfactorily performed.
[3]   ATTACH completed copy of 2-TOP-068-01 used for this test.
B.
[4]   NOTIFY Instrument Maintenance to make available a print out of recorder charts used for this test, and ENSURE they are accurately marked (date, time, parameter, recorder number).
The results recorded on Measuring and Test Equipment (M&TE) Log in SMP-9.0.
[5]   NOTIFY the Unit 2 US/SRO of the test completion and system alignment.
[2]
8.0   RECORDS A. QA Records Completed Test Package B. Non-QA Records None
VERIFY Post-test calibration of permanent plant instruments used to record quantitative acceptance criteria has been satisfactorily performed and RECORD the results on Appendix C, Permanent Plant Instrumentation Log.
[3]
ATTACH completed copy of 2-TOP-068-01 used for this test.
[4]
NOTIFY Instrument Maintenance to make available a print out of recorder charts used for this test, and ENSURE they are accurately marked (date, time, parameter, recorder number).
[5]
NOTIFY the Unit 2 US/SRO of the test completion and system alignment.
8.0 RECORDS A.
QA Records Completed Test Package B.
Non-QA Records None


Shutdown from Outside the Main       2-PTI-068-13 Control Room               Rev. 0000 Page 27 of 36 Appendix A (Page I of 1)
Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 27 of 36 Appendix A (Page I of 1)
Test Procedures/instructions Reference Review Date NOTES
Test Procedures/instructions Reference Review Date NOTES
: 1)     Additional copies of this table may be made as necessary.
: 1)
: 2)     Initial and date indicates review has been completed for impact.
Additional copies of this table may be made as necessary.
PROCEDURE/                                     IMPACT       INITIALAND DATE.
: 2)
INSTRUCTION             REVISIONICHANGES       Yes/No       (NIA for no change)
Initial and date indicates review has been completed for impact.
Unit 2 FSAR Table 14.2-1                 Amendment 109 (Sheets 77, 78 and 79 of 89)
PROCEDURE/
Integrated Hot Functional Tests Test Summary NRC Regulatory Guide 1.68.2,           Revision 1, July 1978 Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants.
IMPACT INITIALAND DATE.
WBN Unit 2, Technical                   Dated 2/28/2012 Specifications, RCS Pressure and Temperature Limits Report (PTLR)                   Rev 0, March 2011 2-TOP 068-01, Main Control Room               Rev 0 Inaccessibility 2-AOI-27, Main Control Room                   Rev 0 Inaccessibility 2-IMI-63.001, Low Steam line                   Rev 0 Pressure SI Block 2-IMI-63.002, Low Pressurizer                 Rev 0 Pressure SI Block 2-TI-57.002, Verification of Normal           Rev 0 Position For Nor-Aux Switches and Various Handswitches 2-TSD-68-6, Test Scoping                       Rev 0 Document for RCS Cooldown From Hot Functional Testing
INSTRUCTION REVISIONICHANGES Yes/No (NIA for no change)
Unit 2 FSAR Table 14.2-1 Amendment 109 (Sheets 77, 78 and 79 of 89)
Integrated Hot Functional Tests Test Summary NRC Regulatory Guide 1.68.2, Revision 1, July 1978 Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants.
WBN Unit 2, Technical Dated 2/28/2012 Specifications, RCS Pressure and Temperature Limits Report (PTLR)
Rev 0, March 2011 2-TOP 068-01, Main Control Room Rev 0 Inaccessibility 2-AOI-27, Main Control Room Rev 0 Inaccessibility 2-IMI-63.001, Low Steam line Rev 0 Pressure SI Block 2-IMI-63.002, Low Pressurizer Rev 0 Pressure SI Block 2-TI-57.002, Verification of Normal Rev 0 Position For Nor-Aux Switches and Various Handswitches 2-TSD-68-6, Test Scoping Rev 0 Document for RCS Cooldown From Hot Functional Testing


WBN               Shutdown from Outside the Main           2-PTI-068-13 Unit 2                         Control Room                   Rev. 0000 Page 28 of 36 Appendix B (Page 1 of 1)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 28 of 36 Appendix B (Page 1 of 1)
Temporary Condition Log.
Temporary Condition Log.
Date NOTE These steps will be N/A'd if no temporary condition existed. Additional copies of this table may be made as necessary.
Date NOTE These steps will be N/A'd if no temporary condition existed. Additional copies of this table may be made as necessary.
PERFORMED                 RETURNED TO NORMAL ITEM       TEMPORARY CONDITION             Step   Performed BylDate       Step   ReturedBylDate No.             DESCRIPTION                 No.     :..CV BylDate   :No.           CV BylDate
PERFORMED RETURNED TO NORMAL ITEM TEMPORARY CONDITION Step Performed BylDate Step ReturedBylDate No.
                                                              /                             /
DESCRIPTION No.
I                             /
:..CV BylDate
I                             I I                             I I                             /
:No.
I                             I I                             I I                             I I                             I I                             I
CV BylDate
                                                              /                             I I                             I I                             I
/  
___ ____ __ _ ____ __ _  __ _  _ __/                               _.        /__
/
I  
/
I I
I I
I  
/
I I
I I
I I
I I
I I
/
I I
I I
I
_ __/  
/__  


WBN           Shutdown from Outside the Main       2-PTI-068-13 Unit 2                 Control Room                 Rev. 0000 Page 29 of 36 Appendix C (Page 1 of 4)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 29 of 36 Appendix C (Page 1 of 4)
Permanent Plant Instrumentation Log Date
Permanent Plant Instrumentation Log Date
                                                            .USED FOR.*:
.USED FOR.*:
INSTRUMENT               FILLED AND     PLACED IN:'     QUANTITATIVE.
INSTRUMENT FILLED AND PLACED IN :'
OR                   VENTED'       SERVICE'         ACC CRIT                       POST-TEST CALIBRATION INSTRUMENT CAL DUE/                                                       POST,-EST CAL       ACCEPTABLE' LOOP"# CAL DATE 3    INITIDATE     INITIDATE     YES       NO         DATE 2           INITIALIDATE 2-TI-68-1C 2-TI-68-24C 2-TI-68-43C 2-TI-68-65C 2-LI-68-325C 2-LI-68-326C 2-PI-68-336C 2-PI-68-337C 2-PI-1-IC 2-PI-1-8C 2-PI-1-19C 2-PI-1-26C 2-FI-3-142C 2-FI-3-163C
QUANTITATIVE.
OR VENTED' SERVICE' ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUE/
POST,-EST CAL ACCEPTABLE' LOOP"#
CAL DATE3 INITIDATE INITIDATE YES NO DATE 2 INITIALIDATE 2-TI-68-1C 2-TI-68-24C 2-TI-68-43C 2-TI-68-65C 2-LI-68-325C 2-LI-68-326C 2-PI-68-336C 2-PI-68-337C 2-PI-1-IC 2-PI-1-8C 2-PI-1-19C 2-PI-1-26C 2-FI-3-142C 2-FI-3-163C


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WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 30 of 36 Appendix C (Page 2 of 4)
Permanent Plant Instrumentation Log Date USED FOR.
Permanent Plant Instrumentation Log Date USED FOR.
INSTRUMENT               FILLED AND     PLACED IN       QUANTITATIVE OR                   VENTED1       SERVICE 1        ACC CRIT                   POST-TEST CALIBRATION INSTRUMENT CAL DUEl                                                     POST-TEST CAL     ACCEPTABLE 2 LOOP # CAL DATE 3     INITIDATE     INITIDATE     1YES     NO       DATE 2         INITIALUDATE 2-FI-3-155C 2-FI-3-147C 2-FI-3-170C 2-LI-3-164C 2-LI-3-156C 2-LI-3-148C 2-LI-3-171C 2-PI-62-92C 2-FI-62-93C 2-PI-62-81C 2-TI-62-80C
INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE2 LOOP #
CAL DATE 3 INITIDATE INITIDATE 1YES NO DATE 2 INITIALUDATE 2-FI-3-155C 2-FI-3-147C 2-FI-3-170C 2-LI-3-164C 2-LI-3-156C 2-LI-3-148C 2-LI-3-171C 2-PI-62-92C 2-FI-62-93C 2-PI-62-81C 2-TI-62-80C


WBN           Shutdown from Outside the Main     2-PTI-068-13 Unit 2                 Control Room               Rev. 0000 Page 31 of 36 Appendix C (Page 3 of 4)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 31 of 36 Appendix C (Page 3 of 4)
Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT               FILLED AND     PLACED IN'     QUANTITATIVE OR                   VENTED1       SERVICE1         ACC CRIT                   POST-TEST CALIBRATION INSTRUMENT CAL DUEl                                                     POST-TEST CAL     ACCEPTABLE2 LOOP # CAL DATE 3    INITIDATE     INIT/DATE     YES       NO       DATE 2        INITIALIDATE 2-LI-62-129C 2-FI-63-173c 2-FI-63-91 C 2-FI-67-92C 2-FI-67-61C 2-FI-67-62C 2-TI-74-38C 2-T1 40C 2-FI-70-164C 2-LI-70-63C 2-LI-70-99C
Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN' QUANTITATIVE OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE2 LOOP #
CAL DATE3 INITIDATE INIT/DATE YES NO DATE2 INITIALIDATE 2-LI-62-129C 2-FI-63-173c 2-FI-63-91 C 2-FI-67-92C 2-FI-67-61C 2-FI-67-62C 2-TI-74-38C 2-T1 40C 2-FI-70-164C 2-LI-70-63C 2-LI-70-99C


WBN                       Shutdown from Outside the Main                             2-PTI-068-13 Unit 2                                   Control Room                                 Rev. 0000 Page 32 of 36 Appendix C (Page 4 of 4)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 32 of 36 Appendix C (Page 4 of 4)
Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT                                     FILLED AND'               PLACED IN               QUANTITATIVE OR                                           VENTED 1               SERVICE 1                  ACC CRIT                                         POST-TEST CALIBRATION INSTRUMENT             CAL DUE/                                                                                               POST-TEST CAL                   ACCEPTABLE2 LOOP #             CAL DATE 3                 1iNITIDATE                INITIDATE               YES             NO:           .. DATE 2                     INITIALIDATE 2-PI-70-17C 2-FI-70-159C 2-FI-70-165C 1 These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and vented may be identified as Not Applicable. (N/A) 2   May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitative acceptance criteria data.
Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND' PLACED IN QUANTITATIVE OR VENTED 1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUE/
3 Enter the Cal Date for instruments/loops that do not have a "Cal Due Date". The Cal Date shall be within 12 months at the start of the test. Enter "CD" and the date for Cal Due Date and 'C" and the date for Cal Date.
POST-TEST CAL ACCEPTABLE2 LOOP #
CAL DATE 3 1 iNITIDATE INITIDATE YES NO:
DATE 2 INITIALIDATE 2-PI-70-17C 2-FI-70-159C 2-FI-70-165C 1
These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and vented may be identified as Not Applicable. (N/A) 2 May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitative acceptance criteria data.
3 Enter the Cal Date for instruments/loops that do not have a "Cal Due Date". The Cal Date shall be within 12 months at the start of the test. Enter "CD" and the date for Cal Due Date and 'C" and the date for Cal Date.


WBN         Shutdown from Outside the Main             2-PTI-068-13 Unit 2               Control Room                     Rev. 0000 Page 33 of 36 Figure 1 (Page 1 of 1)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 33 of 36 Figure 1 (Page 1 of 1)
RCS Cooldown Rate Graph Date 0 30     60 90   120 150   180   210   .240       270   300   330   360   390 420 450 480 rime (minutes)
RCS Cooldown Rate Graph Date 0
_ 100F/hr ....   !Uihr Plotted By:                                                               Both Axes in OF
30 60 90 120 150 180 210  
.240 270 300 330 360 390 420 450 480 rime (minutes)
_ 100F/hr....  
!Uihr Plotted By:
Both Axes in OF


WBN         Shutdown from Outside the Main                 2-PTI-068-13 Unit 2                 Control Room                       Rev. 0000 Page 34 of 36 Figure 2 (Page 1 of 1)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 34 of 36 Figure 2 (Page 1 of 1)
Pressurizer Cooldown Rate Graph Date u 30   60 go 120   150   180   210   240     270     300   330   360 390   420 450 480 Time (minutes)
Pressurizer Cooldown Rate Graph Date u
_OOF/hr .... 50F/hr Plotted By:                                                                   Both Axes in OF
30 60 go 120 150 180 210 240 270 300 330 360 390 420 450 480 Time (minutes)
_OOF/hr....
50F/hr Plotted By:
Both Axes in OF


WBN           Shutdown from Outside the Main           2-PTI-068-13 Unit 2                   Control Room                 Rev. 0000 Page 35 of 36 Figure 3 (Page 1 of 2)
WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 35 of 36 Figure 3 (Page 1 of 2)
Pressure/Temperature Limit Curves Date RCS COOLDOWN WITH ONE RCP RUNNING 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 2   1500 1400
Pressure/Temperature Limit Curves Date RCS COOLDOWN WITH ONE RCP RUNNING 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 2 1500 1400
'i 1300 W 1200
'i 1300 W 1200
: 0. 1100 (0
: 0. 1100 (0
C) 1000 W*
C) 1000 W*
0     25   50 75 100   125 150 175   200   225 250   275 300   325 350 375 400 RCS TEMP (F)
0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 RCS TEMP (F)
Plotted By:
Plotted By:


Shutdown from Outside the Main               2-PTI-068-1 3 Control Room                      Rev. 0000 Page 36 of 36 Figure 3 (Page 2 of 2)
Shutdown from Outside the Main Control Room 2-PTI-068-1 3 Rev. 0000 Page 36 of 36 Figure 3 (Page 2 of 2)
PressurelTemperature Limit Curves Date RCS COOLDOWN WITH TWO RCPs RUNNING zoJU '
PressurelTemperature Limit Curves Date RCS COOLDOWN WITH TWO RCPs RUNNING zoJU '
2400.
2400.
2300.
2300.
2200-2100-2000.
2200-2100-2000.
1900 1800-100-               UNACCEPTABLE I, 1600/
1900 1800-100-UNACCEPTABLE I, 1600/
1500 a-1400 U, 1300-(0 uJ1200                                                                        z a.1100.                                                                      I U,                                                                         /
1500 1400 1300-1200 z
C) 1000 900 800 700 600 500 400                   -  I                               10F/H 300                      IO/H             _CCP__L 200 100 0  I                                                                   0 0     25   50 75   100   125 150   175     200 225 250 275 300    325 350  375 400 RCS TEMP (T)
1100.
a-U, (0uJ a.
U, C) 1000 900 800 700 600 500 400 300 200 100 0
I
/
I 10F/H IO/H
_CCP__L I
0 300 325 350 375 400 0
25 50 75 100 125 150 175 200 225 250 275 RCS TEMP (T)
Plotted By:}}
Plotted By:}}

Latest revision as of 10:28, 11 January 2025

Submittal of Pre-op Test Instruction
ML13071A324
Person / Time
Site: Watts Bar Tennessee Valley Authority icon.png
Issue date: 03/06/2013
From: Hruby R
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML13071A324 (38)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 March 6, 2013 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391

Subject:

Watts Bar Nuclear Plant (WBN) Unit 2 - Submittal of Pre-op Test Instruction The following approved WBN Unit 2 Pre-op Test Instruction (PTI) is enclosed:

PTI NUMBER Rev.

TITLE 2-PTI-068-13 0

Shutdown from Outside the Main Control Room If you have any questions, please contact Nick Welch at (423) 365-7820.

Respectfully, Raymond A. Hruby, Jr.

General Manager, Technical Services Watts Bar Unit 2 Enclosure

U.S. Nuclear Regulatory Commission Page 2 March 6, 2013 cc (Enclosure):

U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381

WATTS BAR NUCLEAR PLANT UNIT 2 PREOPERATIONAL TEST TITLE: Shutdown from Outside the Main Control Room Instruction No: 2-PTI-068-13 Revision No: 0000 PREPARED BY: R. D. Dobbs PR REVIEWED BY: M. David Riden INT NAME I SIGNATURE DATE:

iJ,32/3/zO-DATE: i~~ac PRINT NAME / SIGNATURE INSTRUCTION APPROVAL JTG MEETING No:

3 a/ 0 ?-),

JTG CHAIRMAN:

APPROVED BY:

1F DATE: Z/2///3 DATE:

/Z'//

V PFIEOPERAT1ONXL STARTbJP MANAGER TEST RESULTS APPROVAL JTG MEETING No:

JTG CHAIRMAN:

APPROVED BY:

PREOPERATIONAL STARTUP MANAGER DATE:

DATE:

SMP-8.0, Administration of Preoperational Test instructions, Appendix B 12/07/2010

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 2 of 36 Revision Log Revision Affected or Change Effective Page Number Date Numbers Description of RevisionlChange 0000 All Initial Issue - Unit 2 PTI developed from Unit 1 PTI-068-13, Revision 0.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 3 of 36 Table of Contents

1.0 INTRODUCTION

4 1.1 Test Objectives...............................................

4 1.2 S co p e........................................................................

............................................... 4

2.0 REFERENCES

5 2.1 Perform ance References.........................................................................................

5 2.2 Developmental References.......................................

5 3.0 PRECAUTIONS AND LIMITATIONS............................................................................

8 4.0 PREREQUISITE ACTIONS.........................................................................................

11 4.1 P relim inary A ctions..............................................................................................

.. 11 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies......................

16 4.3 Field P reparations................................................................................................

.. 16 4.4 A pprovals and Notifications.....................................................................................

16 5.0 ACCEPTANCE CRITERIA.................................................

e........................................ 17 6.0 PERFORMANCE..................................................................................................

18 7.0 POST PERFORMANCE ACTIVITY......................................................................

.26 8.0 R EC O R DS..................................................................................................................

26 Appendix A:

Test Procedureslinstructions Reference Review...............................

27 Appendix B:

Temporary Condition Log...................................................................

28 Appendix C:

Permanent Plant Instrumentation Log...............................................

29 Figure 1:

RCS Cooldown Rate Graph................................................................

33 Figure 2:

Pressurizer Cooldown Rate Graph....................................................

34 Figure 3:

Pressure/Temperature Limit Curves.................................. 35

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 4 of 36 Date

1.0 INTRODUCTION

1.1 Test Objectives A.

Demonstrate that the Reactor Coolant System (RCS) can be cooled down in a controlled manner from Hot Standby to Hot Shutdown conditions from outside the Main Control Room (MCR), without exceeding Technical Specification cool down limits.

B. Demonstrate the ability to cool down the plant in a controlled manner from the Auxiliary Control Room (ACR) utilizing the Residual Heat Removal (RHR)

System.

C.

The plant can be maintained in a stable Hot Standby condition from outside the main control room for 30 minutes.

1.2 Scope This Preoperational Test Instruction (PTI) administratively controls performance of 2-TOP-068-01, which incorporates 2-AOI-27, Main Control Room Inaccessibility.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 5 of 36 Date

2.0 REFERENCES

2.1 Performance References A.

SMP-7.0, Control Of Cleanness, Layup, And Flushing B.

SMP-9.0, Conduct of Test C.

2-PTI-068-01, Hot Functional Test D.

2-TOP 068-01, Rev 0, Main Control Room Inaccessibility E.

2-SI-68-44, RCS Temperature/Pressure Limits and Pressurizer Temperature Limits 2.2 Developmental References A.

Unit 2 Final Safety Analysis Report (FSAR) - Amendment 109, Table 14.2-1 (Sheets 77, 78 and 79 of 89) Integrated Hot Functional Tests Test Summary B.

Drawings

1.

Electrical

a.

2-45W751-13, Rev 0, Wiring Diagram 480V Reac Mov Bd 2A1-A Single Line Sh-4

b.

2-45W751-14, Rev 0, Wiring Diagram 480V Reac Mov Bd 2B1-B Single Line Sh-4

c.

45B2766-3F, Rev C, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 3F

d.

45B2766-17F, Rev D, Wiring Diagram 480V Reac Mov Bd 2A1-A CONN DIAG COMPT 17F

e.

45B2768-3F, Rev D, Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 3F

f.

45B2768-16, Rev 4, F Wiring Diagram 480V Reac Mov Bd 2B1-B CONN DIAG COMPT 16F

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 6 of 36 Date 2.2 Developmental References (continued)

2.

Logic/Control

a.

2-47W610-3-3, Rev 4, Electrical Control Diagram Auxiliary Feedwater System

b.

2-47W610-30-2, Rev 2, Electrical Control Diagram Ventilation System

c.

2-47W610-47-1, Rev 4, Electrical Control Diagram Turbo Generator Cont Sys

d.

2-47W610-62-1, Rev 4, Electrical Control Diagram Chemical &

Volume Control Sys

e.

2-47W610-63-1, Rev 8, Electrical Control Diagram Safety Injection System

f.

1-47W610-67-1, Rev 29, Electrical Control Diagram ERCW System

g.

2-47W610-68-1, Rev 3, Electrical Control Diagram Reactor Coolant System

h.

2-47W610-68-4, Rev 3, Electrical Control Diagram Reactor Coolant System

i.

2-47W610-68-6, Rev 2, Electrical Control Diagram Reactor Coolant System

j.

1-47W610-70-1, Rev 28, Electrical Control Diagram Component Cooling Water System

k.

2-47W610-72-1, Rev 5, Electrical Control Diagram Containment Spray System

1.

2-47W610-74-1, Rev 6, Electrical Control Diagram Residual Heat Removal System

m.

2-47W610-77-3, Rev 1, Electrical Control Diagram Waste Disposal System

3.

Instruments & Controls

a.

2-47W600-52, Rev 2, Electrical Instruments and Controls

b.

2-47W600-55, Rev 0, Electrical Instruments and Controls

c.

2-47W600-58, Rev 0, Electrical Instruments and Controls

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 7 of 36 Date 2.2 Developmental References (continued)

d.

47W600-57, Rev 10, Electrical Instruments & Controls

e.

47W600-60, Rev 8, Electrical Instruments & Controls C.

Documents

1.

NRC Regulatory Guide 1.68.2, Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants, Revision 1, July 1978.

2.

WBN Unit 2, Technical Specifications, dated 2/28/2012

a.

Section 3.4.3, RCS Pressure and Temperature (P/T) Limits

b.

Section 5.2.2, Minimum Shift Crew Composition

3.

NPG-SDD-WBN2-68-4001, Rev 2

4.

NPG-SDD-WBN2-68-4001, Rev 2, Appendix B, PTLR

5.

WBT-D-2776, Design Specification 67904, Rev 10

6.

OPDP-1, Rev 23, Conduct of Operations

7.

2-AOI-27, Rev 0, Main Control Room Inaccessibility

8.

2-IMI-63.001, Rev 0, Low Steam line Pressure SI Block

9.

2-IMI-63.002, Rev 0, Low Pressurizer Pressure SI Block

10. 2-TI-57.002, Rev 0, Verification of Normal Position For Nor-Aux Switches and Various Handswitches
11.

2-TSD-68-6, Rev 0, Test Scoping Document for RCS Cooldown From Hot Functional Testing

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 8 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS A.

Standard precautions shall be followed for working around energized electrical equipment in accordance with TVA Safety Manual Procedure 1021.

B. Steps may be repeated if all components cannot be tested in a step. However, if the test has been exited, prerequisite steps are required to be re-verified and a Chronological Test Log (CTL) entry made.

C.

Discrepancies between component ID tags and the description in a procedure/instruction do not require a Test Deficiency Notice (TDN) in accordance with SMP-14.0, if the UNIDs match, exclusive of place-keeping zeros and train designators (e.g. 2-HS-31-468 vs. 2-HS-031-0468) and the noun description are sufficient to identify the component. If the component label needs to be changed, a Tag Request Form (TR Card) should be processed in accordance with TI-12.14. Make an entry in the CTL and continue testing.

D.

All wires removed/lifted from a terminal shall be identified and taped or covered with an insulator to prevent personnel or equipment hazard and possible spurious initiations. The wires should be grouped together and labeled with the work implementing document number that required them to be lifted if left unattended.

E.

All open problems are to be tracked by a corrective action document and entered on the appropriate system punchlist.

F.

Problems identified during the test shall be annotated on the Chronological Test Log from SMP-9.0 including a description of the problem, the procedure step when/where the problem was identified, corrective action steps taken to resolve the problem, and the number of the corrective action document, if one was required.

G.

Observe all Radiation Protection (RP) requirements when working in or near radiological areas.

H. Control room observers, who are additional Operations personnel separate from the shutdown crew, shall remain in the Main Control Room. As a minimum, an SRO designated to have the control room command function and and two ROs shall remain in the MCR as control room observers. Additional Operations personnel, who are not confined to the MCR, report to the control room observers and shall NOT assist the shutdown crew nor communicate information to them except in an emergency.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 9 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)

Control room observers shall assume control of the plant should any emergencies or unsafe conditions arise during this test that are beyond the responsibilities or capabilities of the limited personnel or equipment involved in controlling the plant from the Auxiliary Control Room.

J.

Termination Criteria: The test shall be terminated and control of the unit returned to the Main Control Room in a safe and orderly manner if any of the following conditions occur:

1.

SRO in the Main or Auxiliary Control Room or Test Director believes there is a loss of control of any function needed to safely control the unit.

2.

RCS pressure is less than 1900 psig prior to blocking PZR low pressure Safety Injection.

3.

A condition occurs which has the potential to damage equipment or injure personnel.

4.

Safety Injection occurs.

5.

Steam Generator Narrow Range Level less than 0% or greater than 90%.

6.

Pressurizer Level less than 17% or greater than 92%.

7.

Loss of Offsite Power.

K. Control room observers shall perform non-safety related activities that would not be required during an actual remote shutdown. These activities provide protection for non-safety related equipment from damage during the transient and include the placement of equipment into standby status when no longer required. These activities shall be recorded in the chronological test log and reviewed at the completion of the test to assess their impact on the validity of the test performance.

L.

The shutdown crew shall not receive communications from the MCR except in an emergency to protect personnel or equipment. Such communications may invalidate the objectives of this test and should be recorded in the chronological test log.

M. Only that equipment for which credit would be taken in performing an actual remote plant shutdown shall be used for this test in order to satisfy the Acceptance Criteria.

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 10 of 36 Date 3.0 PRECAUTIONS AND LIMITATIONS (continued)

N. Reactor Coolant temperature shall not be reduced at a rate that exceeds Technical Specification cooldown limits of 100°F in any one hour period.

Cooldown should be performed at a rate of no more than 50°F/hour.

0.

Pressurizer temperature shall not be reduced at a rate that exceeds 200OF in any one hour period. Pressurizer cooldown rate should not exceed 100IF in any one hour.

P.

Reactor Coolant System temperature and pressure shall be determined at least once each 30 minutes to be within the Pressure/Temperature Curve for plant cooldown.

Q.

Pressurizer Spray should NOT normally be initiated if the temperature difference between the Pressurizer and spray fluid is greater than 100 0F, although higher differential temperatures are acceptable for a few cycles in the life of the plant. Under no circumstances shall Pressurizer Spray be intiated if the temperature difference between the Pressurizer and the spray fluid is equal to or greater than 2600F. Any initations where the temperature difference is greater than 260OF shall be reported to Engineering for evaluation and accounted for in thermal cycle monitoring in the licensing basis. Auxiliary spray flow from charging pump should be intiated slowly.

R.

2-PTI-068-01, Hot Functional Test (HFT), contains prerequisites, the lineups for plant support systems, instrumentation, and controls associated with HFT, which includes this PTI.

S.

During the performance of 2-TOP-68-01, Operations personnel are required to initial and date the steps as they are performed. In addition, the Test Engineer (TE) shall record in the Chronological Test Log the actual equipment or equipment loop which was used to perform this test.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 11 of 36 Date 4.0 PREREQUISITE ACTIONS NOTE Preliminary action steps may be performed in any order with Test Directors approval.

4.1 Preliminary Actions

[1]

VERIFY the test/performance copy of this Preoperational Test Instruction (PTI) is the current revision including any change notices and as needed, each test person assisting in this test has the current revision including any change notices.

[2]

OBTAIN copies of the applicable forms from the latest revision of SMP-9.0, and ATTACH to this PTI for use during the PTI performance.

[3]

ENSURE changes to the references listed on Appendix A, Test Procedure/Instruction Reference Review, have been reviewed, and determined not to adversely affect the test performance.

[4]

VERIFY current revisions and change paper for referenced drawings has been reviewed and determined NOT to adversely affect the test performance, and ATTACH documentation of current drawing revision numbers and change paper that were reviewed to the data package.

[5]

EVALUATE punchlist items on Open Watts Bar Integrated Task Equipment List (WITEL) and ENSURE they will NOT adversely affect the test performance.

[6]

ENSURE the minimum shutdown crew composition, as defined by OPDP-1, Conduct of Operations, is available for the performance of this test: Shift Manager (SRO) = 1, Unit Supervisor (SRO) = 1, Shift Technical Advisor (STA) =1, Reactor Operator (RO) = 2, and Assistant Unit Operator (AUO) = 5].

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 12 of 36 Date 4.1 Preliminary Actions (continued).

  • [7]

ENSURE the minimum observation crew is available for performance of this test: SRO designated to have the control room command function = 1, UOs for control board oversight and 2-SI-68-44 performance = 2.

[8]

ENSURE required Component Testing has been completed prior to start of test.

[9]

ENSURE outstanding Design Change Notices (DCN's),

Engineering Document Construction Releases (EDCR's) or Temporary Alterations (TA's) do NOT adversely impact testing, and ATTACH documentation of DCN's, EDCR's and TA's that were reviewed to the data package.

[10]

ENSURE a review of outstanding Clearances has been coordinated with Operations for impact to the test performance, and RECORD in Appendix B, Temporary Condition Log.

[11]

VERIFY System cleanness as required for the performance of this test has been completed in accordance with SMP-7.0.

[12]

VERIFY plant instruments, listed on Appendix C, Permanent Plant Instrumentation Log, are placed in service and are within their calibration interval.

[13]

VERIFY Measuring and Test Equipment (M&TE) required for test performance has been (as required) filled, vented, place in service and recorded on Measuring and Test Equipment Log in SMP-9.0.

[14]

VERIFY M&TE calibration due dates will support the completion of this test performance.

[15]

VERIFY the Unit 2 Plant Computer System 261 is in service.

[16]

VERIFY the Unit 2 Annunciator System 55 is in service.

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 13 of 36 Date 4.1 Preliminary Actions (continued)

[17]

ENSURE System 55, Annunciator and Sequential Events Recording System applicable Terminal Block (TBK) switches [in Panel 2-M-21] are ON, the applicable Master Switches are ON, and window software input(s) are ENABLED for the following Annunciator windows:

A.

2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-D, M-1 THRU M-6 MOTOR OVERLOAD B.

2-XA-55-1B Annunciator Panel in 2-M-1, Window 14-E, M-1 THRU M-6 MOTOR TRIPOUT C.

2-XA-55-5B Annunciator Panel in 2-M-5, Window 95-E, RCP BD 2A UV/CNTL PWR FAILURE/TRANSFER D.

2-XA-55-5B Annunciator Panel in 2-M-5, Window 96-E, RCP BD 2B UV/CNTL PWR FAILURE/TRANSFER E.

2-XA-55-5B Annunciator Panel in 2-M-5, Window 97-E, RCP BD 2C UV/CNTL PWR FAILURE/TRANSFER F.

2-XA-55-5B Annunciator Panel in 2-M-5, Window 98-E, RCP BD 2D UV/CNTL PWR FAILURE/TRANSFER G.

2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-A, RCP BD 2AI2BI2CI2D H. 2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-B, ACR PNL 2-L-1 1A

1.

2-XA-55-6F Annunciator Panel in 2-M-6, Window 148-C, ACR PNL 2-L-1 1 B

[18]

VERIFY the following annunciator windows on 2-M-6 are clear:

A.

Window 148-B, ACR PNL 2-L-1 1A B.

Window 148-C, ACR PNL 2-L-11B

[19]

ENSURE components contained within the boundaries of this test are under the jurisdictional control of Preoperational Startup Engineering (PSE) and/or Plant Operations.

[20]

ENSURE the test performance personnel have been notified and are available to support the test.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 14 of 36 Date 4.1 Preliminary Actions (continued)

[211 PERFORM a pretest walk down on equipment to be tested to ensure no conditions exist that will impact test performance.

[22]

CONDUCT a pretest briefing with Test and Operations personnel in accordance with SMP-9.0.

[231 ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the Backup Control Center sound powered phone system:

A.

6.9 KV Shutdown Board Room (Train A)

B.

6.9 KV Shutdown Board Room (Train B)

C.

480V Shutdown Board Room (Unit 2)

D.

Reactor MOV Board Room (Unit 2)

[24]

ENSURE communications are available between the following designated locations and the Auxiliary Control Room using the plant telephone system:

A.

6.9 KV Shutdown Board Room (Train A)

B.

6.9 KV Shutdown Board Room (Train B)

C.

480V Shutdown Board Room (Unit 2)

D.

Reactor MOV Board Room (Unit 2)

E.

6.9 KV Reactor Coolant Pump (RCP) Boards F.

Main Control Room G.

Auxiliary Building, EL 692', East side, near Turbine Driven (TD) Auxiliary Feedwater (AFW) pump area.

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 15 of 36 Date 4.1 Preliminary Actions (continued)

[25]

VERIFY HFT is being performed with the RCS at Hot Standby Conditions, and.'

RECORD RCS Temperature from 2-TI-68-1, LOOP 1 HL TEMP, on 2-M-5.

OF (greater than or equal to 350°F)

[26]

ESTABLISH additional qualified Operations crew as directed by the Shift Manager (SM) in the MCR who can take control of the plant should any emergencies or unsafe conditions arise during the performance of this test. (See Precautions And Limitations 3.0H)

[27]

VERIFY/CLOSE the following breakers at 480V Reactor MOV Board 2A1-A (2-MCC-213-A1):

A.

SIS CL ACCUM 3 OUT ISOL, (2-FCV-63-80), Shunt Trip Breaker, 2-BKR-63-80A, at Cubicle 17F2.

B.

SIS CL ACCUM 1 OUT ISOL, (2-FCV-63-1 18), Shunt Trip Breaker, 2-BKR-63-118A, at Cubicle 3F2.

[28]

VERIFYICLOSE the following breakers at 480V Reactor MOV Board 2B1-B (2-MCC-213-B1):

A.

SIS CL ACCUM 2 OUT ISOL, (2-FCV-63-98), Shunt Trip Breaker, 2-BKR-63-98A, at Cubicle 3F2.

B.

SIS CL ACCUM 4 OUT ISOL, (2-FCV-63-67), Shunt Trip Breaker, 2-BKR-63-67A, at Cubicle 16F2.

[29]

VERIFY 2-PTI-068-01 prerequisites are complete for the 557°F plateau.

[30]

VERIFY the Condensate Storage Tank B is at normal operating level. (Greater than 200,000 gallons)..

[31]

ENSURE the System and Equipment Status Control, NGDC-PI-8, Preoperational Configuration Log has been evaluated.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 16 of 36 Date 4.2 Special Tools, Measuring and Test Equipment, Parts, and Supplies

[1]

VERIFY a M&TE Qualified Stopwatch, 0-60 minutes,

+/-0.1 second accuracy is available.

[2]

VERIFY four sets of Backup (Shutdown) Control Center sound powered telephones are available.

[3]

ESTABLISH a means of identifying the Main Control Room observation crew and Aux Control Room shutdown crew for this test performance.

4.3 Field Preparations None 4.4 Approvals and Notifications

[1]

OBTAIN permission of the Preoperational Startup Manager to start the test.

Preoperational Startup Manager Signature Date

[2]

OBTAIN the Unit 2 (U2) Supervisors (US/SRO) or Shift Managers (SM) authorization.

U2 US/SRO/SM Signature Date

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 17 of 36 5.0 Date ACCEPTANCE CRITERIA A.

Plant cooldown is performed from outside the MCR from Hot Standby [TAVG of 450°F (425°F - 4750F)] to Hot Shutdown (TAVG between 200°F and 350'F) conditions, without exceeding the Technical Specification cooldown rate limit of 1 00°F/Hr as plotted on Figure 1. (Steps 6.0[8]F and 6.0[13])

B.

The RHR System is used to cool down the Reactor Coolant System at least 50 0F, from outside the MCR, without exceeding the Technical Specification cooldown rate limit of 100°FIHr as plotted on Figure 1. (Steps 6.0[12]D and 6.0[13])

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 18 of 36 Date 6.0 PERFORMANCE NOTES

1) Any activities performed that are outside the scope of this test will be recorded in the Chronological Test Log by the TE and evaluated for their impact on the validity of total test performance after this PTI is completed.
2)

Step 6.0[1] ensures Tech Spec compliance and must not be communicated with shutdown crew unless limit is about to be exceeded.

[1]

INITIATE applicable sections of 2-SI-68-44, RCS Temperature/Pressure Limits And Pressurizer Temperature Limits, and ACCESS ICS screens HC and HCRGRPH to monitor RCS and Pzr Temperature/Pressure Limits from ICS to ensure Tech Spec criteria NOT violated.

MCR Observer Date

[2]

ANNOUNCE over the public address system to notify plant personnel of the control transfer from the U-2 Main Control Room to the U-2 Auxiliary Control Room.

[3]

ELECTRONICALLY MARK the following MCR chart recorders by depressing the keyboard button and entering 2-PTI-068-13 denoting the start of process control from outside the Main Control Room:

A.

Pressurizer (PZR) Pressure (2-PR-68-340) [2-M-5]

B.

PZR Level (2-LR-68-339) [2-M-5]

C.

HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]

D.

HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]

E.

HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]

F.

HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 19 of 36 Date 6.0 PERFORMANCE (continued)

G.

HL Pressure (2-PR-68-63) [2-M-5]

H. Steam Generator (SG) Level % (2-LR-3-43) [2-M-4]

I.

SG Level % (2-LR-3-98) [2-M-4]

J.

SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]

K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]

[4]

TRANSFER process control from the MCR to ACR in accordance with 2-TOP-068-01, Section 2.1.

A.

RECORD time at which all Aux Control Room shutdown personnel are assembled in the Aux Control Room.

Time B.

RECORD time at which each 2-TOP-068-01 checklist (ACR, #1, #2, and #3) is complete below:

Checklist Time Initial ACR

  1. 1
  1. 2
  1. 3 C.

RECORD time process control transfer from the MCR to ACR is complete, the time the last checklist (ACR, #1, #2, and #3) is complete from step above.

Process Control in ACR Time

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 20 of 36 Date 6.0 PERFORMANCE (continued)

[5]

ESTABLISH Hot Standby conditions in accordance with 2-TOP-068-01, and START stopwatch when stable Hot Standby conditions are attained.

M&TE

[6]

MAINTAIN stable Hot Standby conditions from the ACR for a minimum of 30 minutes to ensure control of the unit in accordance with 2-TOP-068-01 and, RECORD total time Hot Standby maintained before commencing plant cooldown.

Elapsed Time minutes S CCAUTION RCS Cooldown rate should not exceed 50°F/hour.

[7]

MONITOR appropriate Cooldown Pressure-Temperature Curves of the appropriate Figure 3 Curves, and PLOT every 30 minutes during all cooldown operations to ensure acceptable region maintained.

[8]

INITIATE plant cooldown from Hot Standby to Hot Shutdown conditions in accordance with 2-TOP-068-01, Section 2.2, and PERFORM the following:

A.

RECORD RCS Loop temperatures (Hot Standby

-greater than or equal to 3500F)

UNID Temperature Panel Initial CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C oF 2-L-1 0 2-TI-68-43C OF 2-L-10 2-TI-68-65C OF 2-L-10

Shutdown from Outside the Main Control Room 2-PTI-068-13 Rev. 0000 Page 21 of 36 Date 6.0 PERFORMANCE (continued)

B.

RECORD RCS average temperature from Step 6.0[8]A by adding all four temperatures and dividing by four.

Average Temp.

OF Initials Verified Date Date C.

START stopwatch, and PLOT the following temperatures at time zero and at 15 minute intervals:

RCS temperature using 2-TI-68-1 C on Figure 1.

PZR temperature as determined by Pressurizer Pressure indication for T-sat on Figure 2 using steam tables located in storage locker.

D. RECORD RCS loop temperatures when Hot Shutdown condition is established. (less than 3500F)

UNID Temperature Panel

Initial, CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C

-F 2-L-1 0 2-TI-68-43C OF 2-L-1 0 2-TI-68-65C OF 2-L-1 0

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 22 of 36 Date 6.0 PERFORMANCE (continued)

E.

RECORD RCS average temperature from Step 6.0[8]D by adding all four temperatures and dividing by four.

Average Temp.

OF Initials Verified Date Date F.

VERIFY all recorded temperatures in Step 6.0[8]D are less than 3500F. (Acc Crit 5.OA)

CAUTION RCS Cooldown rate should not exceed 50°F/hour.

NOTE Plant conditions warrant that only one train of RHR is needed to perform cooldown during HFT, and should be identified in the Chronological Test Log by the TE.

[9]

ESTABLISH RCS cooldown utilizing RHR in accordance with 2-TOP-068-01.

[10]

WHEN RHR System is placed in service, THEN

.RECORD RCS loop temperatures UNID Temperature Panel Initial :7..!:'CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C TF 2-L-10 2-TI-68-43C TF 2-L-10 2-TI-68-65C TF 2-L-10

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 23 of 36 Date 6.0 PERFORMANCE (continued)

[11]

RECORD RCS average temperature from Step 6.0[10] by adding all four temperatures and dividing by four.

Average Temp.

OF Initials Verified Date Date

[12]

LOWER RCS average temperature to 2750F (270°F - 280°F) using RHR System from outside the MCR in accordance with 2-TOP-068-01, Section 2.2.

A.

RECORD RCS loop temperatures:

.UNID Temperature.:

Panel.

Initial CV 2-T1-68-1C OF 2-L-10 2-TI-68-24C OF 2-L-1 0 2-TI-68-43C OF 2-L-10 2-TI-68-65C OF 2-L-10 B.

RECORD RCS average temperature from Step 6.0[12]A by adding all four temperatures and dividing by four.

Average Temp.

OF Initials Date Verified Date

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 24 of 36 Date 6.0 PERFORMANCE (continued)

C.

DETERMINE temperature in Step 6.0[10] minus temperature in Step 6.0[12]A:

Temperatures UNID (Step 6.0[10] -Step 6.0[12])

INITIAL CV 2-T1-68-1C OF 2-TI-68-24C OF 2-TI-68-43C OF 2-TI-68-65C OF D. VERIFY all calculated temperatures recorded in Step 6.0[12]C are greater than or equal to 500F.

(Acc Crit 5.0B)

[13]

VERIFY cooldown rate plotted on Figure 1 does not exceed the Technical Specification limit of 1OO0 F/hour.

(Acc Crit 5.0B)

[14]

STOP the stopwatch, and DISCONTINUE plotting RCS temperature.

[15]

TRANSFER process control from the ACR to MCR in accordance with 2-TOP-068-01, Section 2.3.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 25 of 36 Date 6.0 PERFORMANCE (continued)

[16]

ELECTRONICALLY MARK the following MCR recorders denoting the end of process control from the Auxiliary Control Room:

A.

PZR Pressure (2-PR-68-340).[2-M-5]

B.

PZR Level (2-LR-68-339) [2-M-5]

C.

HL & CL Temperature (Leg 1) (2-TR-68-1) [2-M-5]

D.

HL & CL Temperature (Leg 2) (2-TR-68-24) [2-M-5]

E.

HL & CL Temperature (Leg 3) (2-TR-68-43) [2-M-5]

F.

HL & CL Temperature (Leg 4) (2-TR-68-65) [2-M-5]

G.

HL Pressure (2-PR-68-63) [2-M-5]

H. SG Level % (2-LR-3-43) [2-M-41 I.

SG Level % (2-LR-3-98) [2-M-41 J.

SG 1 & 2 Pressure (2-PR-1-2) [2-M-4]

K. SG 3 & 4 Pressure (2-PR-1-23) [2-M-4]

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 26 of 36 Date 7.0 POST PERFORMANCE ACTIVITY

[1]

VERIFY the following:

A.

Post-test calibration of the M&TE used to record quantitative acceptance criteria has been satisfactorily performed.

B.

The results recorded on Measuring and Test Equipment (M&TE) Log in SMP-9.0.

[2]

VERIFY Post-test calibration of permanent plant instruments used to record quantitative acceptance criteria has been satisfactorily performed and RECORD the results on Appendix C, Permanent Plant Instrumentation Log.

[3]

ATTACH completed copy of 2-TOP-068-01 used for this test.

[4]

NOTIFY Instrument Maintenance to make available a print out of recorder charts used for this test, and ENSURE they are accurately marked (date, time, parameter, recorder number).

[5]

NOTIFY the Unit 2 US/SRO of the test completion and system alignment.

8.0 RECORDS A.

QA Records Completed Test Package B.

Non-QA Records None

Shutdown from Outside the Main 2-PTI-068-13 Control Room Rev. 0000 Page 27 of 36 Appendix A (Page I of 1)

Test Procedures/instructions Reference Review Date NOTES

1)

Additional copies of this table may be made as necessary.

2)

Initial and date indicates review has been completed for impact.

PROCEDURE/

IMPACT INITIALAND DATE.

INSTRUCTION REVISIONICHANGES Yes/No (NIA for no change)

Unit 2 FSAR Table 14.2-1 Amendment 109 (Sheets 77, 78 and 79 of 89)

Integrated Hot Functional Tests Test Summary NRC Regulatory Guide 1.68.2, Revision 1, July 1978 Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants.

WBN Unit 2, Technical Dated 2/28/2012 Specifications, RCS Pressure and Temperature Limits Report (PTLR)

Rev 0, March 2011 2-TOP 068-01, Main Control Room Rev 0 Inaccessibility 2-AOI-27, Main Control Room Rev 0 Inaccessibility 2-IMI-63.001, Low Steam line Rev 0 Pressure SI Block 2-IMI-63.002, Low Pressurizer Rev 0 Pressure SI Block 2-TI-57.002, Verification of Normal Rev 0 Position For Nor-Aux Switches and Various Handswitches 2-TSD-68-6, Test Scoping Rev 0 Document for RCS Cooldown From Hot Functional Testing

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 28 of 36 Appendix B (Page 1 of 1)

Temporary Condition Log.

Date NOTE These steps will be N/A'd if no temporary condition existed. Additional copies of this table may be made as necessary.

PERFORMED RETURNED TO NORMAL ITEM TEMPORARY CONDITION Step Performed BylDate Step ReturedBylDate No.

DESCRIPTION No.

..CV BylDate
No.

CV BylDate

/

/

I

/

I I

I I

I

/

I I

I I

I I

I I

I I

/

I I

I I

I

_ __/

/__

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 29 of 36 Appendix C (Page 1 of 4)

Permanent Plant Instrumentation Log Date

.USED FOR.*:

INSTRUMENT FILLED AND PLACED IN :'

QUANTITATIVE.

OR VENTED' SERVICE' ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUE/

POST,-EST CAL ACCEPTABLE' LOOP"#

CAL DATE3 INITIDATE INITIDATE YES NO DATE 2 INITIALIDATE 2-TI-68-1C 2-TI-68-24C 2-TI-68-43C 2-TI-68-65C 2-LI-68-325C 2-LI-68-326C 2-PI-68-336C 2-PI-68-337C 2-PI-1-IC 2-PI-1-8C 2-PI-1-19C 2-PI-1-26C 2-FI-3-142C 2-FI-3-163C

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 30 of 36 Appendix C (Page 2 of 4)

Permanent Plant Instrumentation Log Date USED FOR.

INSTRUMENT FILLED AND PLACED IN QUANTITATIVE OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE2 LOOP #

CAL DATE 3 INITIDATE INITIDATE 1YES NO DATE 2 INITIALUDATE 2-FI-3-155C 2-FI-3-147C 2-FI-3-170C 2-LI-3-164C 2-LI-3-156C 2-LI-3-148C 2-LI-3-171C 2-PI-62-92C 2-FI-62-93C 2-PI-62-81C 2-TI-62-80C

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 31 of 36 Appendix C (Page 3 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND PLACED IN' QUANTITATIVE OR VENTED1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUEl POST-TEST CAL ACCEPTABLE2 LOOP #

CAL DATE3 INITIDATE INIT/DATE YES NO DATE2 INITIALIDATE 2-LI-62-129C 2-FI-63-173c 2-FI-63-91 C 2-FI-67-92C 2-FI-67-61C 2-FI-67-62C 2-TI-74-38C 2-T1 40C 2-FI-70-164C 2-LI-70-63C 2-LI-70-99C

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 32 of 36 Appendix C (Page 4 of 4)

Permanent Plant Instrumentation Log Date USED FOR INSTRUMENT FILLED AND' PLACED IN QUANTITATIVE OR VENTED 1 SERVICE1 ACC CRIT POST-TEST CALIBRATION INSTRUMENT CAL DUE/

POST-TEST CAL ACCEPTABLE2 LOOP #

CAL DATE 3 1 iNITIDATE INITIDATE YES NO:

DATE 2 INITIALIDATE 2-PI-70-17C 2-FI-70-159C 2-FI-70-165C 1

These items may be initialed and dated by personnel performing the task. Instrumentation not required to be filled and vented may be identified as Not Applicable. (N/A) 2 May be identified as Not Applicable (N/A) if instrument was not used to verify/record quantitative acceptance criteria data.

3 Enter the Cal Date for instruments/loops that do not have a "Cal Due Date". The Cal Date shall be within 12 months at the start of the test. Enter "CD" and the date for Cal Due Date and 'C" and the date for Cal Date.

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 33 of 36 Figure 1 (Page 1 of 1)

RCS Cooldown Rate Graph Date 0

30 60 90 120 150 180 210

.240 270 300 330 360 390 420 450 480 rime (minutes)

_ 100F/hr....

!Uihr Plotted By:

Both Axes in OF

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 34 of 36 Figure 2 (Page 1 of 1)

Pressurizer Cooldown Rate Graph Date u

30 60 go 120 150 180 210 240 270 300 330 360 390 420 450 480 Time (minutes)

_OOF/hr....

50F/hr Plotted By:

Both Axes in OF

WBN Shutdown from Outside the Main 2-PTI-068-13 Unit 2 Control Room Rev. 0000 Page 35 of 36 Figure 3 (Page 1 of 2)

Pressure/Temperature Limit Curves Date RCS COOLDOWN WITH ONE RCP RUNNING 2500 2400 2300 2200 2100 2000 1900 1800 1700 1600 2 1500 1400

'i 1300 W 1200

0. 1100 (0

C) 1000 W*

0 25 50 75 100 125 150 175 200 225 250 275 300 325 350 375 400 RCS TEMP (F)

Plotted By:

Shutdown from Outside the Main Control Room 2-PTI-068-1 3 Rev. 0000 Page 36 of 36 Figure 3 (Page 2 of 2)

PressurelTemperature Limit Curves Date RCS COOLDOWN WITH TWO RCPs RUNNING zoJU '

2400.

2300.

2200-2100-2000.

1900 1800-100-UNACCEPTABLE I, 1600/

1500 1400 1300-1200 z

1100.

a-U, (0uJ a.

U, C) 1000 900 800 700 600 500 400 300 200 100 0

I

/

I 10F/H IO/H

_CCP__L I

0 300 325 350 375 400 0

25 50 75 100 125 150 175 200 225 250 275 RCS TEMP (T)

Plotted By:

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